Updated on 2024/05/16

写真a

 
URITANI Akira
 
Organization
Graduate School of Engineering Applied Energy 2 Professor
Graduate School
Graduate School of Engineering
Undergraduate School
School of Engineering Energy Science and Engineering
Title
Professor

Degree 1

  1. Doctor of Engineering ( 1992.3   Nagoya University ) 

Research Interests 1

  1. neutrons, radiations, standard, laser, BNCT

Research Areas 2

  1. Others / Others  / Radiation detection

  2. Others / Others  / Nuclear Engineering

Current Research Project and SDGs 4

  1. Development of Neutron detector

  2. BNCT

  3. Neutron Standard

  4. Radiation detection by using optical fiber

Research History 7

  1. 三浦学園中部大学   工学部   非常勤講師

    1989.4 - 1990.3

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    Country:Japan

  2. 豊田理化学研究所奨励研究員

    1989.4 - 1990.3

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    Country:Japan

  3. 名古屋大学   工学部   助手

    1990.4 - 1998.6

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    Country:Japan

  4. 名古屋大学   大学院工学研究科   准教授

    1998.7 - 2001.3

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    Country:Japan

    Notes:助教授

  5. 独立行政法人 産業技術総合研究所   計測標準研究部門   主任研究員

    2001.4 - 2005.3

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    Country:Japan

  6. 名古屋大学   大学院工学研究科   教授

    2005.4 - 2021.3

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    Country:Japan

  7. 核融合科学研究所   客員教授   客員教授

    2013.4 - 2015.3

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    Country:Japan

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Education 2

  1. Nagoya University   Graduate School, Division of Engineering   nuclear engineering

    - 1989.3

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    Country: Japan

  2. Nagoya University   Faculty of Engineering   nuclear engineering

    - 1984.3

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    Country: Japan

Professional Memberships 17

  1. 応用物理学会   理事

    2020.4 - 2022.3

  2. 応用物理学会   放射線分科会幹事長

    2012.4 - 2014.3

  3. 日本放射線安全管理学会   理事

    2006.4 - 2022.5

  4. 日本原子力学会   編集委員

    2003.4 - 2007.3

  5. 日本アイソトープ協会   編集委員

    2001.4 - 2004.3

  6. 応用物理学会   諮問委員

    2014.2 - 2016.2

  7. 応用物理学会   放射線分科会副幹事長

    2002.4 - 2004.3

  8. 日本原子力学会   中部支部幹事

    2015.4 - 2017.3

  9. 応用物理学会   編集委員

    2002.4 - 2004.3

  10. 日本原子力学会   放射線利用技術の新展開研究専門委員会委員

    2002.4 - 2004.3

  11. 日本原子力学会   プログラム編成委員

    2001.4 - 2005.3

  12. 日本原子力学会   中部支部幹事

    2000.4 - 2003.3

  13. 応用物理学会   放射線分科会講演世話人

    2000.4 - 2002.3

  14. 日本原子力学会   原子力・放射線施設計装技術の高度化研究専門委員会委員

    1998.4 - 2000.3

  15. 応用物理学会   放射線分科会幹事 1991-1993,1997-1999,2000-2001,2006-2008

  16. 日本中性子科学会

  17. 日本中性子捕捉療法学会

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Committee Memberships 15

  1. 京都大学複合原子力科学研究所研究共同利用研究委員会   委員  

    2021.4 - 2023.3   

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    Committee type:Other

  2. 京都大学複合原子力科学研究所研究計画委員会   委員  

    2021.4 - 2023.3   

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    Committee type:Other

  3. 原子力システム研究開発事業事後評価委員会   委員  

    2019.10 - 2020.3   

  4. E-JUSTプロジェクトフェーズ3国内支援委員会専門部会工学ワーキング・グループ   委員  

    2019.10 - 2020.3   

  5. 原子力システム研究開発事業審査委員会   委員  

    2019.7 - 2020.3   

  6. 東京大学大学院工学研究科原子力専攻共同利用運営委員会   委員  

    2019.5 - 2023.3   

  7. 公益社団法人日本工学協会 事業企画委員会   委員  

    2019.5 - 2020.6   

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    Committee type:Other

  8. 日本工学教育事業企画委員会   委員  

    2019.5 - 2020.6   

  9. 京都大学複合原子力科学研究所運営委員会   京都大学複合原子力科学研究所運営委員  

    2019.4 - 2023.3   

  10. 公益財団法人名古屋産業科学研究所企画運営委員会   委員  

    2019.1 - 2020.6   

  11. 科学研究費委員会   専門委員  

    2018.12 - 2020.11   

  12. 独立行政法人製品評価技術基盤機構JCSS技術委員会   放射線・放射能・中性子分科会委員  

    2018.7 - 2021.6   

  13. 大学加速器連携ネットワークによる人材育成等プログラム運営委員会   委員  

    2018.4 - 2022.3   

  14. 一般社団法人日本放射線安全管理学会第17回学術大会   大会長  

    2018.1 - 2018.12   

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    Committee type:Academic society

  15. 愛知県自然環境保全審議会   委員  

    1997.4 - 2000.3   

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Awards 1

  1. フェロー

    2023.3   日本原子力学会  

 

Papers 266

  1. Estimation of nuclear properties in a deuteron–lithium target using JENDL/DEU-2020 for IFMIF and similar irradiation facilities Invited Reviewed

    Takeo Nishitani, Sachiko Yoshihashi, Yuuki Tanagami, Shota Amano, Akira Uritani, Saerom Kwon, Keitaro Kondo, Kohki Kumagai, Kentaro Ochiai, Satoshi Sato

    Fusion Engineering and Design   Vol. 202   page: 114320   2024.5

  2. First demonstration of a single-end readout position-sensitive optical fiber radiation sensor inside the Fukushima Daiichi Nuclear Power Station based on wavelength-resolving analysis

    Terasaka, Y; Sato, Y; Uritani, A

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1062   2024.5

  3. Compton Imaging Using Pixelated TlBr Semiconductor Detector Invited Reviewed

    Keitaro Hitomi, Motohiro Matsumura, Kenichi Watanabe, Shusuke Maruyama, Mitsuhiro Nogami, and Uritani Akira

    Sensors and Materials   Vol. 36 ( 1 ) page: 225 - 233   2024.3

  4. Precise thermoluminescence glow curve analysis of BeO ceramic plates with slow heating rates

    Sasaki, E; Sugioka, N; Chang, WS; Matsumoto, S; Negishi, T; Nagasaka, K; Yoshihashi, S; Uritani, A; Watanabe, K; Okada, G; Koba, Y; Shinsho, K

    JOURNAL OF MATERIALS SCIENCE-MATERIALS IN ELECTRONICS   Vol. 34 ( 31 )   2023.11

  5. A new application technique of a position-sensitive liquid light guide Cerenkov counter for the simultaneous position detection of <SUP>90</SUP>Sr/<SUP>90</SUP>Y and <SUP>137</SUP>Cs radioactivity

    Terasaka, Y; Uritani, A

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1049   2023.4

  6. Neutron/y-ray discrimination based on the property and thickness controls of scintillators using Li glass and LiCAF (Ce) in a y-ray field

    Kaburagi, M; Shimazoe, K; Terasaka, Y; Tomita, H; Yoshihashi, S; Yamazaki, A; Uritani, A; Takahashi, H

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1046   2023.1

  7. Measurements of <i>γ</i>-rays and neutrons in BNCT irradiation field using thermoluminescent phosphor

    Shinsho, K; Oh, R; Tanaka, M; Sugioka, N; Tanaka, H; Wakabayashi, G; Takata, T; Chang, WS; Matsumoto, S; Okada, G; Sugawara, S; Sasaki, E; Watanabe, K; Koba, Y; Nagasaka, K; Yoshihashi, S; Uritani, A; Negishi, T

    JAPANESE JOURNAL OF APPLIED PHYSICS   Vol. 62 ( 1 )   2023.1

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    Language:Japanese  

    DOI: 10.35848/1347-4065/ac971e

    Web of Science

  8. Evaluation of heat removal performance of a sealed Li target for an accelerator-driven neutron source of Boron Neutron Capture Therapy at Nagoya University

    Honda, S; Yoshihashi, S; Hamaji, Y; Shen, JJ; Tsuchida, K; Nishitani, T; Kiyanagi, Y; Tsurita, Y; Watanabe, K; Yamazaki, A; Uritani, A

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1042   2022.11

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  9. Development of a Sealed Li target as an accelerator-driven neutron source for Boron neutron capture therapy at Nagoya University

    Honda, S; Yoshihashi, S; Tomita, S; Tsuchida, K; Kiyanagi, Y; Tsurita, Y; Watanabe, K; Yamazaki, A; Uritani, A

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1040   2022.10

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  10. 光ファイバを用いた新方式片側読み出し型放射線分布測定法に関する基礎研究 Invited Reviewed

    寺阪 祐太、渡辺 賢一、瓜谷 章

    放射線   Vol. 47 ( 3 ) page: 89 - 96   2022.10

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  11. γ-Ray measurements in boron neutron capture therapy using BeO ceramic thermoluminescence dosimeter

    Tanaka, M; Oh, R; Sugioka, N; Tanaka, H; Takata, T; Wakabayashi, G; Sugawara, S; Watanabe, K; Uritani, A; Yoshihashi, S; Nagasaka, K; Okada, G; Negishi, T; Shinsho, K

    JOURNAL OF MATERIALS SCIENCE-MATERIALS IN ELECTRONICS   Vol. 33 ( 25 ) page: 20271 - 20279   2022.9

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  12. Neutronics Analyses of the Radiation Field at the Accelerator-Based Neutron Source of Nagoya University for the BNCT Study

    Nishitani, T; Yoshihashi, S; Tanagami, Y; Tsuchida, K; Honda, S; Yamazaki, A; Watanabe, K; Kiyanagi, Y; Uritani, A

    JOURNAL OF NUCLEAR ENGINEERING   Vol. 3 ( 3 ) page: 222 - 232   2022.9

  13. Evaluation of Induced Radioactivity Generated during LHD Deuterium Plasma Experiments*)

    Yoshihashi, S; Yamada, H; Kobayashi, M; Nishitani, T; Yamazaki, A; Isobe, M; Ogawa, K; Uritani, A

    PLASMA AND FUSION RESEARCH   Vol. 17   2022.8

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    Language:Japanese  

    DOI: 10.1585/pfr.17.2405096

    Web of Science

  14. Theoretical and experimental estimation of the relative optically stimulated luminescence efficiency of an optical-fiber-based BaFBr:Eu detector for swift ions

    Hirata, Y; Sato, T; Watanabe, K; Ogawa, T; Parisi, A; Uritani, A

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 59 ( 7 ) page: 915 - 924   2022.7

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  15. First demonstration of a novel single-end readout type position-sensitive optical fiber radiation sensor based on wavelength-resolved photon counting

    Terasaka, Y; Watanabe, K; Uritani, A

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1034   2022.7

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  16. Development of a simple calculation tool of dose distributions in a phantom for boron neutron capture therapy

    Ishikawa, A; Watanabe, K; Yoshihashi, S; Sakurai, Y; Kumada, H; Tanaka, H; Uritani, A; Kiyanagi, Y

    JAPANESE JOURNAL OF APPLIED PHYSICS   Vol. 61 ( 7 )   2022.7

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    DOI: 10.35848/1347-4065/ac7273

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  17. Thermal Neutron Measurement Capability of a Single Crystal CVD Diamond Detector near the Reactor Core Region of UTR-KINKI

    Kobayashi, MI; Yoshihashi, S; Yamanishi, H; Sangaroon, S; Ogawa, K; Isobe, M; Uritani, A; Osakabe, M

    PLASMA AND FUSION RESEARCH   Vol. 17   2022.6

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    DOI: 10.1585/pfr.17.2405045

    Web of Science

  18. Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application

    Nishitani, T; Tanagami, Y; Yoshihashi, S; Tsuchida, K; Yamazaki, A; Uritani, A

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 59 ( 5 ) page: 605 - 613   2022.5

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  19. Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table

    Nishitani, T; Yoshihashi, S; Ogawa, K; Miwa, M; Matsuyama, S; Uritani, A

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 59 ( 4 ) page: 534 - 541   2022.4

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  20. Strain distribution visualization of punched electrical steel sheets using neutron Bragg-edge transmission imaging

    Sasada, S; Takahashi, Y; Takeuchi, K; Hiroi, K; Su, YH; Shinohara, T; Watanabe, K; Uritani, A

    JAPANESE JOURNAL OF APPLIED PHYSICS   Vol. 61 ( 4 )   2022.4

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    DOI: 10.35848/1347-4065/ac5153

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  21. Evaluation of the thermal neutron sensitivity, output linearity, and gamma-ray response of optical fiber-based neutron detectors using Li-glass scintillator

    Ishikawa, A; Watanabe, K; Yamazaki, A; Yoshihashi, S; Imai, S; Masuda, A; Matsumoto, T; Tanaka, H; Sakurai, Y; Nogami, M; Hitomi, K; Uritani, A; Harano, H

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 1025   2022.2

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  22. High-spatial-resolution measurement of magnetization distribution using polarized neutron imaging

    Sasada, S; Hiroi, K; Osanai, K; Shinohara, T; Watanabe, K; Uritani, A

    JAPANESE JOURNAL OF APPLIED PHYSICS   Vol. 60 ( 12 ) page: 126003-1 - 126003-6   2021.12

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    DOI: 10.35848/1347-4065/ac3524

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  23. クルックス管実験に用いられる誘導コイルを利用した理科実験 Reviewed

    森千鶴夫、瓜谷章、神谷均、佐合穣、臼井俊哉

    日本放射線安全管理学会誌   Vol. 20 ( 2 ) page: 45 - 51   2021.12

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    Language:Japanese   Publishing type:Research paper (scientific journal)  

    DOI: 10.11269/jjrsm.20.45

  24. Benchmark Calculation of d-Li Thick Target Neutron Yield by JENDL/DEU-2020 for IFMIF and Similar Facilities

    Nishitani, T; Yoshihashi, S; Kumagai, K; Kondo, K; Uritani, A

    PLASMA AND FUSION RESEARCH   Vol. 16   2021.11

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    DOI: 10.1585/pfr.16.1405104

    Web of Science

  25. Feasibility Study of the One-Dimensional Radiation Distribution Sensing Method Using an Optical Fiber Sensor Based on Wavelength Spectrum Unfolding

    Terasaka, Y; Watanabe, K; Uritani, A; Yamazaki, A; Sato, Y; Torii, T; Wakaida, I

    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE   Vol. 7 ( 4 ) page: 042002-1 - 042002-7   2021.10

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    DOI: 10.1115/1.4048841

    Web of Science

  26. 名古屋大学におけるBNCT用加速器中性子源の開発 Invited

    土田一輝、瓜谷章、鬼柳善明、西谷建夫、吉橋幸子、渡辺賢一、山﨑淳、本田祥梧、辻義之、恒吉達也

    Isotope News   Vol. 777   page: 6 - 11   2021.10

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  27. Evaluation of a one-dimensional position-sensitive quartz optical fiber sensor based on the time-of-flight method for high radiation dose rate applications

    Terasaka, Y; Watanabe, K; Uritani, A

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 996   2021.4

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  28. High heat removal technique for a lithium neutron generation target used for an accelerator-driven BNCT system

    Yoshihashi, S; Tsuneyoshi, T; Tsuchida, K; Furuzawa, D; Honda, S; Watanabe, K; Yamazaki, A; Tsuji, Y; Hamaji, Y; Tokitani, M; Tamura, H; Sagara, A; Kiyanagi, Y; Uritani, A

    JOURNAL OF INSTRUMENTATION   Vol. 16 ( 4 ) page: P04016   2021.4

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  29. First experimental verification of the neutron field of Nagoya University Accelerator-driven neutron source for boron neutron capture therapy

    Watanabe, K; Yoshihashi, S; Ishikawa, A; Honda, S; Yamazaki, A; Tsurita, Y; Uritani, A; Tsuchida, K; Kiyanagi, Y

    APPLIED RADIATION AND ISOTOPES   Vol. 168   2021.2

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  30. Thermal neutron measurement by single crystal CVD diamond detector applied with the pulse shape discrimination during deuterium plasma experiment in LHD Reviewed

    Makoto Kobayashi, MaurizioAngelone, SachikoYoshihashi, KunihiroOgawa, MitsutakaIsobe, TakeoNishitani, SiriyapornSangaroon, ShujiKamio, YutakaFujiwara, TomomiTsubouchi, AkiraUritani, MinoruSakama, MasakiOsakabe, the LHD Experiment Group

    Fusion Engineering and Design   Vol. 161   page: 112063   2020.12

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    Language:Japanese   Publishing type:Research paper (scientific journal)  

    The Pulse shape discrimination (PSD) technique for single crystal CVD diamond detector (SDD) was applied to
    the real-time thermal neutron measurement during the 3rd campaign of Deuterium-Deuterium (D-D) plasma
    experiment in the Large Helical Device (LHD). The PSD method is based upon the different shape of electrical
    pulses produced in diamond by gamma-ray (triangular-shaped pulse) and energetic ions (rectangular-shaped
    pulse), respectively. An improved PSD was developed which makes use of the full width at half maximum
    (FWHM) and the full width at 2/3 of the peak height (FW2/3 PH). These two parameters reflect the difference in
    the pulse shape produced by gamma-rays and energetic ions.
    The performance of this improved PSD technique was first tested irradiating the SDD by gamma-rays from
    60Co and alphas from 241Am radiation sources, respectively. Then, using a 6LiF thermal neutron converter, a
    successful discrimination between gamma-rays and alpha particles and tritons generated by the 6Li(n,α)3H re-
    action induced by neutrons from 252Cf spontaneous fission neutron source was achieved. Thanks to this PSD
    processing technique, the thermal neutron detection efficiency increased about 1.7 times compared to previous
    measurements performed without the PSD technique.
    The real-time thermal neutron measurement by SDD with this enhanced PSD processing was also used during
    D-D plasma discharges in the Large Helical Device (LHD). It was found that both the time integrated counts and
    the time evolution count rate measured by the SDD reproduced well that of the fission chamber used as official
    LHD neutron monitor. The capability of the SDD detector using the PSD technique of precise real-time thermal
    neutron measurement in LHD was demonstrated.

    DOI: 10.1016/j.fusengdes.2020.112063

    Web of Science

  31. Response evaluation of a compact and highly efficient neutron diffractometer for compact accelerator neutron sources Invited

    Sho Imai, Kenichi Watanabe, Astushi Yamazaki, Sachiko Yoshihashi, Akira Uritani, Seiji Tasaki, Setsuo Satoh

    Radiation Protection   Vol. 40 ( 6 ) page: 540 - 544   2020.11

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    Language:English   Publishing type:Research paper (international conference proceedings)  

  32. Observation of neutron emission anisotropy by neutron activation measurement in beam-injected LHD deuterium plasmas Reviewed

    Sugiyama S., Nishitani T., Matsuura H., Isobe M., Ogawa K., Tanaka T., Yoshihashi S., Uritani A., Osakabe M.

    NUCLEAR FUSION   Vol. 60 ( 7 )   2020.7

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    DOI: 10.1088/1741-4326/ab90c9

    Web of Science

  33. Development of Optical-fiber-based Neutron Detector Using Li-glass Scintillator for an Intense Neutron Field Reviewed

    Akihisa Ishikawa, Atsushi Yamazaki, Kenichi Watanabe, Sachiko Yoshihashi, Akira Uritani, Yoshinori Sakurai, Hiroki Tanaka, Ryo Ogawara, Mitsuru Suda, and Tsuyoshi Hamano

    Sensors and Materials   Vol. 32 ( 4 ) page: 1489-1495   2020.4

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    The development of a neutron detector for real-time measurements in an intense neutron field is desired. We are developing a quartz optical-fiber-based neutron detector as a real-time neutron monitor. Thus far, Eu:LiCaAlF6 crystals and LiF/Eu:CaF2 eutectics were used as the scintillators of the quartz optical-fiber-based neutron detectors. These scintillators have high light yields, but relatively long decay time constants, which are limitation factors of the dynamic range of optical-fiber-based neutron detectors. In this paper, we applied a small Li-glass scintillator to a quartz optical-fiber-based neutron detector using an optical fiber with high numerical aperture (NA) and a UV-curable resin with high transmittance. The fabricated detector showed a clear peak corresponding to neutron events in the pulse height distribution. The radiation resistance was evaluated and no deterioration was observed up to 2×1012 n/cm2. The detector output linearity was confirmed up to 450 kcps, which was about ten times larger than that of the detector using the conventional Eu:LiCaAlF6 or LiF/Eu:CaF2 scintillator.

    DOI: doi.org/10.18494/SAM.2020.2748

  34. A comparison between simulation and experimental results for depth profile of Li-6 reaction rate in a water phantom of BNCT using a small Li-6-based scintillator neutron detector with an optical fiber Reviewed

    Ishikawa Akihisa, Yamazaki Atsushi, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira, Tsurita Yukio, Tsuchida Kazuki, Kiyanagi Yoshiaki

    RADIATION MEASUREMENTS   Vol. 133   2020.4

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    DOI: 10.1016/j.radmeas.2020.106270

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  35. Design and Construction of an Imaging beamline at the Nagoya University Neutron Source Reviewed

    Katsuya Hirota, Shogo Awano, Takuhiro Fujiie, Seiso Fukumura, Mayu Hishida, Go Ichikawa,, Sohei Imajo, Ikuya Itoh, Yoshihisa Iwashita, Masaaki Kitaguchi, Yoshiaki Kiyanagi, Yasutoshi Kuriyama, Koki Morikawa, Yu-dai Niinomi, Hirohiko M. Shimizu, Kazuki Tsuchida, Yusuke Tsuchikwa, Yukio Tsurita, Akira Uritani, Kenichi Watanabe, Yutaka Yamagata, Nana Yamamoto, Atsushi Yamazaki, Sachiko Yoshihashi and Tamaki Yoshioka

    EPJ Web Conf.   Vol. 231   page: 05002   2020.3

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    The Nagoya University Accelerator driven Neutron Source (NUANS) is constructed at the main campus of the Nagoya University. The electrostatic accelerator is used with the maximum proton energy and intensity of 2.8MeV, 15mA(42kW) respectively. Two neutron beamlines are designed at NUANS. The BL1 is dedicated to BNCT development. The BL2 is designed for research and development for neutron devices and neutron imaging. The neutrons used for the BL2 are generated by using the (p, n) reaction from a thin beryllium target. We constructed a compact target station for the BL2 and measured the neutron transmission image.

    DOI: 10.1051/epjconf/202023105002

  36. Sensitivity and linearity of optical fiber-based neutron detectors using small Li-6-based scintillators

    Ishikawa Akihisa, Yamazaki Atsushi, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira, Fukuda Kentaro, Koike Akifumi, Ogawara Ryo, Suda Mitsuru, Hamano Tsuyoshi

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 954   page: 161661-1 - 161661-5   2020.2

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    DOI: 10.1016/j.nima.2018.11.120

    Web of Science

  37. Basic study on a LiF-Eu:CaF2 mixed powder neutron scintillator

    Watanabe Kenichi, Mitsuboshi Natsumi, Ishikawa Akihisa, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira, Kawaguchi Noriaki, Yanagida Takayuki, Fukuda Kentaro

    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT   Vol. 954   2020.2

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    DOI: 10.1016/j.nima.2018.09.079

    Web of Science

  38. 箔検電器によるクルックス管からのX 線の線量率測定 Reviewed

    森千鶴夫,緒方良至,秋吉優史,臼井俊哉,村上浩介,羽澄大介,中村嘉行,渡辺賢一,瓜谷章,神谷均,佐合穣,宮川俊晴,田中隆一,掛布智久,森山正樹

      Vol. 69   page: 1-12   2020.1

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    高等学校などで使用されているクルックス管は,一般的に漏洩X線を発生している。X線の線量率の測定に,これらの学校が保有している箔検電器を使う方法を提案した。箔検電器の箔の開き角は電極に与えられた電位に依存して変化する。この電位はX線によって空気中に作られたイオンを集めて減少し箔は閉じて行く。しかし,空気中のイオン密度は周辺の電位や風,および箔検電器に荷電する電荷の正負の影響も受ける。正電荷を荷電した場合に箔が閉じる時間と負電荷を荷電した場合のそれとの幾何平均値をとることによって,電離箱で測定した線量率との間に再現性のある関係を得ることができた。この関係を校正線と呼ぶが,他の同様の市販の箔検電器にも適用できる。

    DOI: 0.3769/radioisotopes.69.1

  39. Development of Optical-fiber-based Neutron Detector Using Li glass Scintillator for an Intense Neutron Field

    Ishikawa, A; Yamazaki, A; Watanabe, K; Yoshihashi, S; Uritani, A; Sakurai, Y; Tanaka, H; Ogawara, R; Suda, M; Hamano, T

    SENSORS AND MATERIALS   Vol. 32 ( 4 ) page: 1489 - 1495   2020

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    DOI: 10.18494/SAM.2020.2748

    Web of Science

  40. Measurement of Thermal and Epithermal Neutron Flux Distribution in the Torus Hall of LHD using Activation Method in the First Deuterium Experiment Campaign Reviewed

    Tomoyo TANAKA, Makoto KOBAYASHI, Sachiko YOSHIHASHI, Akira URITANI, Kenichi WATANABE, Atsushi YAMAZAKI, Takeo NISHITANI, Kunihiro OGAWA and Mitsutaka ISOBE

    Plasma and Fusion Research   Vol. 14   page: 3405162-1 - 3405162-4   2019.11

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    In the Large Helical Device (LHD) of the National Institute for Fusion Science, a deuterium plasma experiment was performed in March 2017. Neutrons with an energy of 2.45 MeV are generated by d (d, n) 3He reactions. The evaluation of this neutron flux in the torus hall, as well as within the LHD vessel, is very important for the decommissioning of the LHD in the future and the radiation shielding for workers and components around the LHD. In this study, we evaluate the spatial distribution of thermal and epithermal neutron flux on the floor level of the LHD torus hall by measuring the neutron activation of gold foils. The flux information obtained in the experiment can be used for the evaluation of radio-activation and the shielding design.

    DOI: 10.1585/pfr.14.340516

  41. Pulsed Neutron Imaging Based Crystallographic Structure Study of a Japanese Sword made by Sukemasa in the Muromachi Period Reviewed

    Kenichi Oikawa, Yoshiaki Kiyanagi, Hirotaka Sato, Kazuma Ohmae, Anh Hoang Pham, Kenichi Watanabe, Yoshihiro Matsumoto, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo, Masato Ohnuma, k, Sigekazu Morito, Takuya Ohba, Akira Uritani, Masakazu Ito

    Neutron Radiography WCNR-11     page: 207-213   2019.10

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    DOI: 207-213

  42. Crystallographic Structure Study of a Japanese Sword Masamitsu made in the 1969 using Pulsed Neutron Imaging Reviewed

    Kazuma Ohmae, Yoshiaki Kiyanagi, Hirotaka Sato, Kenichi Oikawa, Anh Hoang Pham, Kenichi Watanabe, Yoshihiro Matsumoto, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo, Masato Ohnuma, Shigekazu Morito, Takuya Ohba, Akira Uritani, M. Ito

    Neutron Radiography WCNR-11     page: 227-232   2019.10

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    DOI: 227-232

  43. Comparative Study of Ancient and Modern Japanese Swords using Neutron Tomography Reviewed

    Yoshihiro Matsumoto, Kenichi Watanabe, Kazuma Ohmae, Akira Uritani, Yoshiaki Kiyanagi, Hirotaka Sato, Masato Ohnuma, Anh Hoang Pham, Shigekazu Morito, Takuya Ohba, Kenichi Oikawa, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo, Masakazu Ito

    Neutron Radiography WCNR-11     page: 221-226   2019.10

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    DOI: 221-226

  44. Crystallographic Microstructure Study of a Japanese Sword made by Noritsuna in the Muromachi Period by Pulsed Neutron Bragg-Edge Transmission Imaging Reviewed

    Hirotaka Sato, Yoshiaki Kiyanagi, Kenichi Oikawa, Kazuma Ohmae, Anh Hoang Pham, Kenichi Watanabe, Yoshihiro Matsumoto, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo, Masato Ohnuma, Shigekazu Morito, Takuya Ohba, Akira Uritani, Masakazu Itoh

    Neutron Radiography WCNR-11     page: 214-220   2019.10

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    DOI: 214-220

  45. Thermal neutron flux evaluation by a single crystal CVD diamond detector in LHD deuterium experiment Reviewed

      Vol. 44   2019.9

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    DOI: https://doi.org/10.1088/1748-0221/14/09/C09039

  46. Measurement of neutron spectrum using activation method in deuterium plasma experiment at LHD Reviewed

    Tomoyo Tanak, Sachiko Yoshihashi, Makoto Kobayashi, Akira Uritani, Kenichi Watanabe, Atsushi Yamazaki, Takeo Nishitani, Kunihiro Ogawa, MitsutakaIsobe

    Fusion Engineering and Design   Vol. 146   page: 496 - 499   2019.9

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    In the Large Helical Device (LHD) of the National Institute for Fusion Science, the experiments using deuterium plasma were performed from March 2017. Neutrons with the energy of 2.45 MeV are generated by d (d, n) 3He reactions. The evaluation of the neutron flux in the torus hall as well as the LHD vessel is very important for designing the decommissioning of the LHD in the future, and the radiation shielding for workers and components around LHD. In this study, we performed the activation experiments using multiple activation foils to obtain a neutron spectrum in the vacuum vessel of the LHD. The reaction rate of each activation foil was generally consistent with the calculation result by MCNP6. As a result of the unfolding with SAND-II code, we experimentally obtained the neutron spectrum in the vacuum vessel of the LHD for the first time.

    DOI: 10.1016/j.fusengdes.2019.01.005

    Web of Science

  47. Thermal neutron flux evaluation by a single crystal CVD diamond detector in LHD deuterium experiment

    Kobayashi, M; Ogawa, K; Isobe, M; Nishitani, T; Kamio, S; Fujiwara, Y; Tsubouchi, T; Yoshihashi, S; Uritani, A; Sakama, M; Osakabe, M

    JOURNAL OF INSTRUMENTATION   Vol. 14 ( 9 )   2019.9

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  48. Development of thermal neutron moderator for testing boron agents for Boron Neutron Capture Therapy (BNCT) Reviewed

    Ichikawa, G; Tsuchida, K; Kiyanagi, Y; Ishikawa, A; Hirata, Y; Yoshihashi, S; Watanabe, K; Uritani, A; Hamano, T; Ogawara, R; Suda, M; Igawa, K

    JOURNAL OF INSTRUMENTATION   Vol. 14   page: 0   2019.6

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    We developed a thermal neutron source for performance tests of boron agents for
    Boron Neutron Capture Therapy (BNCT) at Neutron exposure Accelerator System for Biological
    Effect Experiments (NASBEE) in National Institute of Radiological Sciences, Japan. The thermal
    neutron flux at the experimental position was measured to be 2:18 108 ncm2s, the cadmium
    ratio was 9:21, and gamma ray dose rate was 2:11 Gyh. The neutron dose rate was estimated to be
    2:96 Gyh. These values indicate that the neutron source can be applicable for tests of boron agents
    although application range is limited. An example of irradiation experiment is described.

    DOI: 10.1088/1748-0221/14/06/T06010

    Web of Science

  49. Basic evaluation of the Eu:BaFBr and Ce:CaF2 hybrid type optical fiber based dosimeter system for correction of quenching effect under carbon ion irradiation Reviewed

    Yuho Hirata, Kenichi Watanabe, Atsushi Yamazaki, Sachiko Yoshihashi, Akira Uritani, Yusuke Koba, Naruhiro Matsufuji, Takayuki Yanagida and Kentaro Fukuda

    Progress in Nuclear Science and Technology   Vol. 6   page: 238-242   2019.2

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    We fabricated the hybrid type optical fiber based dosimeter system using Eu:BaFBr and Ce:CaF2 optically stimulated luminescence (OSL) materials in order to correct the quenching effect under high LET particle irradiation. The fabricated dosimeter probe can obtain signals from both OSL materials through one optical fiber. We investigated the probe response by irradiating it with mono-energetic carbon ions and broad-spectrum ones making the spread-out Bragg peak (SOBP). We demonstrated that the SOBP shape can be improved by correction of the quenching effect using the relationship between the luminescence efficiency and the signal intensity ratio of both OSL materials.

    DOI: 10.15669/pnst.6.238

  50. Development of wide one-dimensional X-ray line sensor in backscatter X-ray imaging system for infrastructure inspection Reviewed

    Kazuya Ohashi, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Hiroyuki Toyokawa, Takeshi Fujiwara, Shinichi Mandai and Hidenori Isa

    Progress in Nuclear Science and Technology   Vol. 6   page: 208-211   2019.2

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    We fabricated a wide one-dimensional X-ray line sensor in backscatter X-ray imaging system. The length and width of the sensitive area of our line sensor is 200 mm and 50 mm, respectively. By using fan-beam X-rays and scanning in the perpendicular direction to the fan-beam plane, two-dimensional backscatter X-ray images can be obtained. In basic experiments, we confirmed that an iron rod placed at the depth of, at least, 9 cm in a concrete brock can be seen by combining our line sensor and C-band linac X-ray generator.

    DOI: 10.15669/pnst.6.208

  51. Response evaluation of Onion-like single Bonner sphere neutron spectrometer using TRUST Eu:LiCAF scintillator Reviewed

    Kenichi Watanabe, Tomoaki Mizukoshi, Atsushi Yamazaki, Sachiko Yoshihashi, Akira Uritani, Tetsuo Iguchi, Tomohiro Ogata, Takashi Muramatsu, Tetsuro Matsumotc and Akihiko Masuda

    Progress in Nuclear Science and Technology   Vol. 6   page: 122-125   2019.2

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    We have developed the single sphere neutron spectrometer with five sensitive layers using the TRUST Eu:LiCAF scintillator and the WLSF readout. We evaluated the energy dependence of the detector response at thermal neutron and 24 keV, 144 keV, 565 keV, 5MeV and 14.8 MeV mono-energetic neutron irradiation fields. The experimentally determined neutron sensitivities are consistent with the Monte Carlo calculations. The detector responses for a bare and a heavy-water moderated 252Cf sources also show good agreement with the expected ones using the Monte Carlo calculations.

    DOI: 10.15669/pnst.6.122

  52. Measurement of Thermal and Epithermal Neutron Flux Distribution in the Torus Hall of LHD using Activation Method in the First Deuterium Experiment Campaign

    Tanaka, T; Kobayashi, M; Yoshihashi, S; Uritani, A; Watanabe, K; Yamazaki, A; Nishitani, T; Ogawa, K; Isobe, M

    PLASMA AND FUSION RESEARCH   Vol. 14   2019

  53. Development of a neutron source for imaging at the electron linac facility in Kyoto University Research Reactor Institute Reviewed

    Yoshiyuki Takahashi, Yoshiaki Kiyanagi, Kenichi Watanabe, Akira Uritani, Tadafumi Sano, Junichi Hori, Ken Nakajima

    Physica B: Condensed Matter   Vol. 551   page: 488-491   2018.12

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    The Kyoto University electron linac, KURRI-LINAC, has been used for executing a project to develop methodology for the integrity evaluation of nuclear fuels, named the N-DeMAIN (Development of Non-Destructive Methods Adapted for Integrity test of Next generation nuclear fuels) project in Japan. As a non-destructive method, the neutron resonance transmission analysis was adopted for the identification and the quantification of nuclide in the fuels. Furthermore, determination of temperature distribution in the fuels based on Doppler broadening was also planned as well as traditional transmission imaging.
    A target-moderator-reflector system (TMRS) and a beam collimator system has been redesigned to obtain the highest intensity with the use of simulation calculation. The neutron beam line is placed at an angle of 135° with respect to the electron beam line. Optimal arrangement of the target and the moderator was investigated. After then, collimator design was performed, and a collimator system to shape the neutron and γ ray beams was designed. Test experiments were performed by using this system.
    Here, we explain the results of design study of the TMRS and the collimator, and the test experiments.

    DOI: doi.org/10.1016/j.physb.2018.06.009

  54. Development of a neutron source for imaging at the electron linac facility in Kyoto University Research Reactor Institute

    Takahashi, Y; Kiyanagi, Y; Watanabe, K; Uritani, A; Sano, T; Hori, J; Nakajima, K

    PHYSICA B-CONDENSED MATTER   Vol. 551   page: 488 - 491   2018.12

  55. Development of x-ray backscatter imaging system for inspection of concrete structure Invited

      Vol. 23 ( 11 ) page: 13-18   2018.11

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  56. Design of Beam Shaping Assembly for an Accelerator-driven BNCT System in Nagoya University Reviewed

    Akira URITANI, Yosuke MENJO, Kenichi WATANABE, Atsushi YAMAZAKI, Yoshiaki KIYANAGI and Kazuki TSUCHIDA

    JPS Conf. Proc.   Vol. 22   page: 011002-1 - 011002-7   2018.11

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    An accelerator-driven compact neutron source for boron neutron capture therapy (BNCT) has been developed in Nagoya University since 2013. A Dynamitron accelerator and a Li target are used to generate neutrons. The 7Li(p, n)7Be nuclear reaction produces neutrons. Since the generated neutrons have considerably high energy, up to one MeV, it is necessary to lower the neutron energy to an epithermal region that is suitable for BNCT. In this work, we have designed a beam shaping assembly (BSA) that lowers the neutron energy and makes beam-like neutrons. The BSA consists of a MgF2 moderator, a lead reflector, a radiation shield and a neutron collimator. The PHITS (Ver.2.66) code has been used to simulate the neutron transport in the BSA. This paper mainly describes two issues. One is the optimization of the shape of the BSA, mainly the moderator, and the other is the dependence of the simulation results on the nuclear data libraries, JENDL-4.0 and ENDF/B-VII.1.

    DOI: 10.7566/JPSCP.22.011002

  57. Construction of the 2nd Beamline of Nagoya University Accelerator-driven Neutron Source (NUANS) Reviewed

    Yusuke Tsuchikawa, Keisuke Abo, Daiki Furuzawa, Katsuya Hirota, Go Ichikawa, Sohei Imajo, Ikuya Ito, Yoshihisa Iwashita, Masaaki Kitaguchi, Yoshiaki Kiyanagi, Yasuhiko Miwata, Kazuya Sato, Hirohiko M. Shimizu, Hayato Takeshita, Kazuki Tsuchida, Yukio Tsurita, Akira Uritani, Kenichi Watanabe, Yutaka Yamagata, Atsushi Yamazaki, and Sachiko Yoshihashi

    JPS Conf. Proc.   Vol. 22   page: 011024-1 - 011024-4   2018.11

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    DOI: 10.7566/JPSCP.22.011024

  58. Improved Design of the Exit of a Beam Shaping Assembly for an Accelerator-driven BNCT System in Nagoya University Reviewed

    Kazuya Sato, Akira Uritani, Kenichi Watanabe, Sachiko Yoshihashi, Atsushi Yamazaki, Yoshiaki Kiyanagi, and Kazuki Tsuchida

    JPS Conf. Proc.   Vol. 22   page: 011003-1 - 011002-7   2018.11

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    DOI: 10.7566/JPSCP.22.011003

  59. Development of One-Dimensional Position-Sensitive Neutron Detector Using TRUST Eu:LiCAF Scintillator Reviewed

    Hiroaki SHIMIZU, Koichi KINO, Setsuo SATO, Kenichi WATANABE, Akira URITANI, Sachiko YOSHIHASHI and Atsushi YAMAZAKI

    JPS Conf. Proc.   Vol. 22   page: 011020-1 - 011002-8   2018.11

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    We developed a one-dimensional position-sensitive neutron detector using Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST Eu:LiCAF) scintillators and a newly proposed wavelength-shifting fiber (WLSF) readout. The proposed position-sensitive WLSF readout consists of a number of WLSFs optically divided to distinguish the scintillation position. We experimentally compared the position sensitivities of the optically divided WLSF type detector and a conventional one using light attenuation in the WLSFs. We concluded that the proposed detector had higher spatial resolution than that of the conventional one. Additionally, we fabricated a prototype version of the optically divided WLSF type detector. We determined the prototype detector had a relative spatial resolution of approximately 20 %.

    DOI: 10.7566/JPSCP.22.011020

  60. Neutron Diagnostics in the Large Helical Device Reviewed

    Mitsutaka Isobe, Kunihiro Ogawa, Takeo Nishitani, Hitoshi Miyake, Takashi Kobuchi, Neng Pu, Hoiroki Kawase, Eiji Takada, Tomoyo Tanaka, Siyuan Li, Sachiko Yoshihashi, Akira Uritani, Jungmin Jo, Sadayoshi Murakami, Masaki Osakabe

    IEEE Transactions on Plasma Science   Vol. 46 ( 6 ) page: 2050 - 2058   2018.6

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    The deuterium operation of the large helical device (LHD) began in March 7, 2017, after long-term preparation and commissioning of apparatuses necessary for execution of the deuterium experiment. A comprehensive set of neutron diagnostics was developed and installed onto LHD through numerous efforts in preparation. Neutron diagnostics play an essential role in both neutron yield management for the radiation safety and extension of energetic-particle physics study in LHD. Neutron flux monitor (NFM) characterized by fast-response and wide dynamic range capabilities is successfully working. Total neutron emission rate reached 3.3×1015(n/s) in the first deuterium campaign of LHD. The highest neutron emission rate was recorded in inward shifted configuration. Neutron yield evaluated by neutron activation system agrees with neutron yield measured with NFM. Performance of vertical neutron camera was demonstrated. Neutron emission profile was inwardly shifted in the inwardly shifted configuration, whereas it was outwardly shifted in the outwardly configuration. Secondary deuterium-tritium neutrons produced by triton burnup in LHD deuterium plasmas were detected for the first time in stellarator/heliotron devices in the world. Similar to total neutron emission rate, the inward shifted configuration provided highest triton burnup ratio.

    DOI: 10.1109/TPS.2018.2836987

    Web of Science

  61. 二種類の光刺激蛍光体と光ファイバーを用いたハイブリッド小型線量計による炭素線照射時に発生する消光現象の補正法の検討

    平田悠歩、山﨑淳、渡辺賢一、吉橋幸子、瓜谷章、古場裕介、松藤成弘、柳田健之、福田健太郎

    放射線   Vol. 43 ( 4 ) page: 139-142   2018.1

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  62. In situ calibration of neutron activation system on the large helical device Reviewed

    N. Pu, T. Nishitani, M. Isobe, K. Ogawa, H. Kawase, T. Tanaka, S. Y. Li, S. Yoshihashi and A. Uritani

    Review of Scientific Instruments   Vol. 88 ( 11 ) page: 113302   2017.11

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    In situ calibration of the neutron activation system on the Large Helical Device (LHD) was performed by using an intense 252Cf neutron source. To simulate a ring-shaped neutron source, we installed a railway inside the LHD vacuum vessel and made a train loaded with the 252Cf source run along a typical magnetic axis position. Three activation capsules loaded with thirty pieces of indium foil-stacked with total mass of approximately 18 g were prepared. Each capsule was irradiated over 15 hours while the train was circulating. The activation response coefficient (9.4 ± 1.2)×10-8 of 115In(n, n')115mIn reaction obtained from the experiment is in good agreement with results by three-dimensional neutron transport calculations using the MCNP 6 code. The activation response coefficients for 2.45 MeV birth neutron and secondary 14.1 MeV neutron from deuterium plasma were evaluated from the activation response coefficient obtained in this calibration experiment.

  63. Correction of quenching effect of a small size OSL dosimeter using Eu:BaFBr and Ce:CaF2

    Hirata Yuho, Watanabe Kenichi, Uritani Akira, Yamazaki Atsushi, Koba Yusuke, Matsufuji Naruhiro, Yanagida Takayuki, Fukuda Kentaro

    RADIATION MEASUREMENTS   Vol. 106   page: 246 - 251   2017.11

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    DOI: 10.1016/j.radmeas.2017.03.043

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  64. <i>In situ</i> calibration of neutron activation system on the large helical device

    Pu, N; Nishitani, T; Isobe, M; Ogawa, K; Kawase, H; Tanaka, T; Li, SY; Yoshihashi, S; Uritani, A

    REVIEW OF SCIENTIFIC INSTRUMENTS   Vol. 88 ( 11 )   2017.11

  65. 名古屋大学における加速器BNCT用システムの開発― Li封入型ターゲットの除熱方法の検討― Invited

    古澤大貴、瓜谷章、渡辺賢一、吉橋幸子、山崎淳、鬼柳善明、土田一輝、辻義之、恒吉達矢、浜地志憲、時谷政行、田村仁、相良明男

      Vol. 4   page: 22-23   2017.9

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  66. Correction of quenching effect of a small size OSL dosimeter using Eu:BaFBr and Ce:CaF2 Reviewed

    Yuho Hirata, KenichiWatanabe, AkiraUritani, AtsushiYamazaki, Yusuke Koba, Naruhiro Matsufuji, TakayukiYanagida, Kentaro Fukuda

    Radiation Measurements   Vol. 106   page: 246-251   2017.4

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    To accurately estimate an actual dose during radiotherapy treatment, dosimeters are required to be inserted into the affected region in a patient's body. Therefore, we are developing a small size dosimeter consisting of optical fibers and optically stimulated luminescence (OSL) elements. We fabricated two types of small size dosimeters using Eu:BaFBr and Ce:CaF2. We measured the Bragg peak of high energy carbon ions in a water equivalent material. OSL materials showed the quenching effect when irradiated by high linear energy transfer (LET) particles. The sensitivity of Eu:BaFBr and Ce:CaF2 monotonically decreased with different coefficients. The ratio of the signal intensity of these two OSL materials can uniquely determine the sensitivity of each OSL material. We corrected the quenching effect of the OSL dosimeters in the spread out Bragg peak with this relationship.

  67. Particle Dependence of Quenching Effect in an Optical-Fiber-Type Optically Stimulated Luminescence Dosimeter

    Hirata Yuho, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira, Koba Yusuke, Naruhiro Matsufuj I, Yanagida Takayuki, Toshito Toshiyuki, Fukuda Kentaro

    SENSORS AND MATERIALS   Vol. 29 ( 10 ) page: 1455 - 1464   2017

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    DOI: 10.18494/SAM.2017.1626

    Web of Science

  68. Upgrade of neutron energy spectrometer with single multilayer Bonner sphere using onion-like structure Reviewed

    T. Mizukoshi, K. Watanabe, A. Yamazaki, A. Uritani, T. Iguchi, T. Ogata and T. Muramatsu

    Journal of Radiation Protection and Research   Vol. 41 ( 3 ) page: 185-190   2016.9

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  69. Quenching Effect in an Optical Fiber Type Small Size Dosimeter Irradiated with 290 MeV·u-1 Carbon Ions Reviewed

      Vol. 41 ( 3 ) page: 222-228   2016.9

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  70. Recent Progress in the Fusion Neutronics 7. Status of the Fusion Neutronics in the Domestic Fusion Facilities

    SUKEGAWA Atsuhiko, URITANI Akira, NISHIMURA Kiyohiko and NISHITANI Takeo

    JOURNAL OF PLASMA AND FUSION RESEARCH   Vol. 92 ( 4 ) page: 282-285   2016.4

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  71. Basic study on response of a small size dosimeter using optical fiber and Ce:CaF2 OSL element

    Hirata, Y.; Watanabe, K.; Yamazaki, A.; Uritani, A.; Koba, Y.; Matsufuji, N.; Yanagida, T.; Fukuda, K.

      Vol. 41 ( 3 ) page: 157-161   2016

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    We fabricated a small size optical fiber type dosimeter system using Ce:CaF2 OSL element. We evaluated basic response of fabricated dosimeter to radiations of X-ray and high-energy carbon ions. When irradiating X-ray, good linearity can be confirmed. With increasing linear energy transfer (LET) of carbon ions, luminescence efficiency of Ce:CaF2 decreases. Compared with the conventional small dosimeter using Eu:BaFBr OSL element, Ce:CaF2 shows a small deterioration in the luminescence efficiency.

  72. Study on neutron energy spectrometer with onion-like single bonner sphere using TRUST Eu:LiCAF scintillator

    Mizukoshi, T.; Watanabe, K.; Yamazaki, A.; Uritani, A.; Iguchi, T.; Ogata, T.; Muramatsu, T.

      Vol. 41 ( 3 ) page: 151-155   2016

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    We fabricated the prototype of a single sphere neutron spectrometer with five sensitive layers using the Transparent FUbber SheeT Eu:LiCaAlF6 (TRUST Eu:LiCAF) scintillator and the wavelength-shifting fibers (WLSFs). We confirmed that the fabricated detector shows a clear neutron peak and can discriminate neutron and gamma-ray events in signal pulse height spectra. We additionally compared the neutron sensitivity between the new TRUST Eu:LiCAF type and the previous LiF-ZnS mixed powder type. The sensitivity of the new one is 40 times higher than that of the previous one.

  73. Study on Effects of Gamma-Ray Irradiation on TlBr Semiconductor Detectors Reviewed

    Motohiro Matsumura, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Norihisa Kimura, Nobumichi Nagano, and Keitaro Hitomi

    JPS Conf. Proc.   Vol. 11   page: 030005-1 - 030005-5   2016

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    DOI: 10.7566/JPSCP.11.030005

  74. Wavelength-shifting fiber signal readout from Transparent RUbber SheeT (TRUST) type LiCaAlF6 neutron scintillator Reviewed

    Kenichi Watanabe, Takuya Yamazaki, Dai Sugimoto, Atsushi Yamazaki, Akira Uritani, Tetsuo Iguchi, Kentaro Fukuda, Sumito Ishidu, Takayuki Yanagida, Yutaka Fujimoto

    Nuclear Instruments and Methods A   Vol. 784   page: 260-263   2015.6

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    As an alternative to the standard 3He neutron detector, we are developing the Transparent RUbber SheeT type (TRUST)Eu doped LiCaAlF6 (Eu:LiCAF)scintillator. This type of neutron scintillator can easily be fabricated as a large area sheet. In order to take advantage of a large area detector, we try to read out scintillation photons using a wavelength-shifting fiber (WLSF) from a TRUSTEu:LiCAF scintillator. The TRUST Eu:LiCAF scintillator with the size of 50x50x5 mm3 was mounted on the WLSF plate and the end of the WLSFs was connected with a PMT. In order to reject high pulse height events induced in the WLSFs, we applied the pulse shape discrimination technique. The gamma-ray intrinsic and neutron
    absolute detection efficiency is evaluated to be 8.8x10^7 and 9x103 cps/ng Cf(2m) for the TRUSTEu:
    LiCAF scintillator with the size of 50x50x5 mm^3.

  75. Development of X-ray backscatter system to inspect the inner structure of concrete Invited

    Hiroyuki Toyokawa, Shinichi Mandai, Akira Uritani, Kenichi Watanabe

        page: 0   2015.5

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    There are more than 700 thousand road bridges, whose lengths are longer than 2 m. Sixteen percent of them were built more than 50 years ago, and their fraction will increase to 40% and 65%, in next 10 years and 20 years, respectively. The maintenance, inspection and repair of them are managed mainly by a local government, which the infrastructures are located. However, the management of the infrastructure is becoming more difficult for the local governments, because of the lack of a financial resource, human resource, and technical knowledge. In Japan, the deterioration of the infrastructures by the sea wind and the salt is serious especially for the roadbed and the reinforced concrete due to the corrosion. Nondestructive inspection methods, which are currently being applied on-site are not enough to measure the degree of damage of concretes, quantitatively. So, a novel method for nondestructive inspection of inner structure of concrete with radiation instrumentation and electron accelerator, which uses X-ray backscatter is being developed. The X-ray backscatter system, which has advantages in highly precise image and one-sided accessibility in inspection, is developed for use in inspecting roadbed and bridge, as a compact and light-weight system. Nondestructive inspection by visualization, using a high resolution X-ray backscatter image for reinforcement bar and a pot-hole inside concrete structure will be possible.

  76. Development of an optical fiber type detector using a Eu:LiCaAlF6 scintillator for neutron monitoring in boron neutron capture therapy Reviewed

    Kenichi Watanabe, Yuya Kawabata, Atsushi Yamazaki, Akira Uritani, Tetsuo Iguchi, Kentaro Fukuda, Takayuki Yanagida

    Nuclear Instruments and Methods in Physics Research A   Vol. A802   page: 1-4   2015

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  77. Portable Neutron Detector Using Ce:LiCaAlF6 Scintillator Reviewed

    Kenichi Watanabe, Takayuki Yanagida, Kentaro Fukuda, Akifumi Koike, Toru Aoki and Akira Uritani

    SENSORS AND MATERIALS   Vol. 27 ( 3 ) page: 269-275   2015

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    We fabricated a prototype portable neutron detector using a Ce:LiCaAlF6 (Ce:LiCAF) scintillator and evaluated its basic performance. The weight of the fabricated detector including the battery is 800 g, significantly less than that of the conventional portable neutron detector, which weighs more than 5 kg. The neutron sensitivity of the fabricated detector is evaluated to be 2.3 cps/(mu Sv/h), comparable to that of the conventional detector. The gamma-ray intrinsic detection efficiency is evaluated to be less than 10(-6). The gamma-ray sensitivity is sufficiently low under ordinary circumstances. The expected count rate of the error counting due to the pile-up effect of gamma-ray-induced events is confirmed to be less than the background count rate for an incident gamma-ray rate of less than 10(4) gammas/s.

  78. Study on fast luminescence component induced by gamma-rays in Ce doped LiCaAlF6 scintillators Reviewed

    Kenichi Watanabe, Yoshiyuki Kondo, Atsushi Yamazaki, Akira Uritani, Tetsuo Iguchi, Noriaki Kawaguchi, Kentaro Fukuda, Sumito Ishizu, Takayuki Yanagida, Yutaka Fujimoto, Akira Yoshikawa

    Radiation Measurements   Vol. 71   page: 158-161   2014.12

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    DOI: 00

  79. Scintillation properties of composite ceramic YAG and its capability on pulse shape descrimination Reviewed

    Takayuki Yanagida, Kenichi Watanabe, Yutaka Fujimoto, Akira Uritani, Hideki Yagi and Takagimi Yanagitani

    JOURNAL OF THE CERAMIC SOCIETY OF JAPAN   ( 122 ) page: 1016-1019   2014.12

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    Transparent ceramic composite of non-doped and Ce-doped YAG was prepared by Konoshima Chemical with the vacuum sintering technique and investigated on pulse shape discrimination capability for functional collimator. Scintillation responses such as X-ray induced radioluminescence and decay time profiles of non-doped and Ce-doped YAG were evaluated. Pulse shape discrimination capability of the composite ceramic was evaluated by Cs-137 662 keV gamma-ray irradiation. As a result, clear separation of gamma-ray events at non-doped or Ce-doped YAG layers was observed in two dimensional histogram by using signal processing with two different shaping times. (C) 2014 The Ceramic Society of Japan. All rights reserved.

    DOI: 10.2109/jcersj2.122.1016

  80. Study on in situ calibration for neutron flux monitor in the Large Helical Device based on Monte Carlo calculations Reviewed

    Y. Nakano, A. Yamazaki, K. Watanabe, A. Uritani, K. Ogawa, M. Isobe

    Rev. Sci. Instrum.   Vol. 85 ( 11 ) page: 11E116-11E116-3   2014.11

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    Neutron monitoring is important to manage safety of fusion experiment facilities because neutrons are generated in fusion reactions. Monte Carlo simulations play an important role in evaluating the influence of neutron scattering from various structures and correcting differences between deuterium plasma experiments and in situ calibration experiments. We evaluated these influences based on differences between the both experiments at Large Helical Device using Monte Carlo simulation code MCNP5. A difference between the both experiments in absolute detection efficiency of the fission chamber between O-ports is estimated to be the biggest of all monitors. We additionally evaluated correction coefficients for some neutron monitors.

    DOI: 10.1063/1.4891049

  81. Progress in development of the neutron profile monitor for the large helical devicea Reviewed

    K. Ogawa, M. Isobe, E. Takada, Y. Uchida, K. Ochiai, H. Tomita, A. Uritani, T. Kobuchi and Y. Takeiri

    Rev. Sci. Instrum.   Vol. 85 ( 11 ) page: 11E110-11E110-3   2014.11

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    The neutron profile monitor stably operated at a high-count-rate for deuterium operations in the Large Helical Device has been developed to enhance the research on the fast-ion confinement. It is composed of a multichannel collimator, scintillation-detectors, and a field programmable gate array circuit. The entire neutron detector system was tested using an accelerator-based neutron generator. This system stably acquires the pulse data without any data loss at high-count-rate conditions up to 8 × 105 counts per second.

    DOI: 10.1063/1.4890399

  82. Wide dynamic range neutron flux monitor having fast time response for the Large Helical Device) Reviewed

    M. Isobe, K. Ogawa, H. Miyake, H. Hayashi, T. Kobuchi, Y. Nakano, K. Watanabe, A. Uritani, T. Misawa, T. Nishitani, M. Tomitaka, T. Kumagai, Y. Mashiyama, D. Ito, S. Kono, M. Yamauchi and Y. Takeiri

    Rev. Sci. Instrum.   Vol. 85 ( 11 ) page: 11E114-11E114-4   2014.11

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    A fast time response, wide dynamic range neutron flux monitor has been developed toward the LHD deuterium operation by using leading-edge signal processing technologies providing maximum counting rate up to ~5 x 10^9 counts/s. Because a maximum total neutron emission rate over 1 x 10^16 n/s is predicted in neutral beam-heated LHD plasmas, fast response and wide dynamic range capabilities of the system are essential. Preliminary tests have demonstrated successful performance as a wide dynamic range monitor along the design.

    DOI: 10.1063/1.4891049

  83. Study on In-Situ Calibration for Neutron Monitor in the Helical Type Fusion Experimental Device Based on Monte Carlo Calculations Reviewed

    Y. Nakano, A. Yamazaki, K. Watanabe, A. Uritani, K. Ogawa, M. Isobe

    Plasma and Fusion Research   Vol. 9   page: 3405141-1 - 3405141-4   2014.10

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    Monte Carlo simulations in design of neutron monitors for fusion experimental devices play an important role
    to evaluate the influence of scattering from various structures and to correct differences between neutron energies from calibration source and fusion plasma. We have developed an automated input file generation code based on finely segmented helical coil approximation. In this paper, we study the optimal number of divisions of segmented geometry from viewpoints of simulation precision and required calculation time. We conclude that results with more than 360 divisions saturate into the result with fully fine simulation. And we evaluate influence of neutron scattering from a miniature train, a railroad and supporting structures used in in-situ calibration experiments at LHD.

  84. Study on Neutron detector using transparent rubber sheet with dispersed small pieces of LiCaAlF6 Scintillator Invited

      Vol. 40 ( 1 ) page: 67-70   2014.3

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  85. 巻頭言 福島復興に向けた放射線計測研究者への期待

    瓜谷章

    放射線   Vol. 39 ( 4 ) page: 151   2014.2

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  86. Neutron TOF Experiments Using Transparent Rubber Sheet Type Neutron Detector with Dispersed Small Pieces of LiCaAlF6 Scintillator Reviewed

    Dai Sugimoto, Kenichi Watanabe, Katsuya Hirota, Atushi Yamazaki, Akira Uritani, Tetsuo Iguchi, Kentaro Fukuda, Sumito Ishidu, Noriaki Kawaguchi, Takayuki Yanagida, Yutaka Fujimoto, Akira Yoshikawa, Hiroyuki Hasemi, Kouichi Kino, Yoshiaki Kiyanagi

    Physics Procedia   Vol. 60   page: 349-355   2014

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  87. Scintillation Properties of LiF-SrF2 and LiF-CaF2 Eutectic Reviewed

    Noriaki Kawaguchi, Takayuki Yanagida, Yutaka Fujimoto, Yuki Furuya, Yoshisuke Futami, Akihiro Yamaji, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Shinji Kajimoto, Hiroshi Fukumura, Shunsuke Kurosawa, Yuui Yokota, Jan Pejchal, Akira Yoshikawa

    Journal of Luminescence   Vol. 144   page: 212-216   2013.12

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    DOI: 10.1016/j.jlumin.2013.07.016

  88. 3. Radiation Measurement in Fusion Facility 3.3 Fundamentals and Applications of Neutron Measurement Invited

    Akira URITANI

    J. Plasma Fusion Research   Vol. 89 ( 10 ) page: 686-690   2013.10

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  89. Neutron Detection with LiCaAlF6 Scintillator Doped with 3d-transition Metal Reviewed

    Noriaki Kawaguchi, Takayuki Yanagida, Yutaka Fujimoto, Yuki Furuya, Yoshisuke Futami, Akihiro Yamaji, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Shinji Kajimoto, Hiroshi Fukumura, Shunsuke Kurosawa, Yuui Yokota, Jan Pejchal, Akira Yoshikawa

    Radiation Measurements   Vol. 55   page: 128-131   2013.8

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    We have developed a novel micro-size dosimeter using an optical fiber probe coupled with a photostimulable storage phosphor, such as BaFBr:Eu2+. Our micro-size dosimeter is based on the concept in which the radiation dose response is temporally compressed by using integrating-type dosimeter elements, such as a photostimulable storage phosphor, and the signal-to-noise ratio is improved to downsize the dosimeter probe. We fabricate the prototype dosimeter probe which has the detectable volume of 100 mm thick and 400 mm diameter and the outer diameter of 900 mm. The lower limit of detectable dose, which is defined as three times the noise level, is evaluated to be 0.9 mGy. This value is much smaller than the typical irradiation dose (a few Gy per treatment) in the radiotherapy. We, therefore, conclude that the proposed micro-size dosimeter can be a promising candidate of in-vivo and on-line dose monitor in the
    radiotherapy.

  90. Development of a Micro-Size Dosimeter Using an Optical Fiber Probe Based on Photostimulable Phosphorescence Reviewed

    Kenichi Watanabe, Atsushi Yamazaki, Kotaro Nakahashi, Hidefumi Miyamae, Akira Uritani, Eiji Ariga

    Radiation Measurements   Vol. 55   page: 64-67   2013.8

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    We have developed a novel micro-size dosimeter using an optical fiber probe coupled with a photostimulable storage phosphor, such as BaFBr:Eu2+. Our micro-size dosimeter is based on the concept in which the radiation dose response is temporally compressed by using integrating-type dosimeter elements, such as a photostimulable storage phosphor, and the signal-to-noise ratio is improved to downsize the dosimeter probe. We fabricate the prototype dosimeter probe which has the detectable volume of 100 mm thick and 400 mm diameter and the outer diameter of 900 mm. The lower limit of detectable dose, which is defined as three times the noise level, is evaluated to be 0.9 mGy. This value is much smaller than the typical irradiation dose (a few Gy per treatment) in the radiotherapy. We, therefore, conclude that the proposed micro-size dosimeter can be a promising candidate of in-vivo and on-line dose monitor in the
    radiotherapy.

  91. Origin of Fast Scintillation Components of LiCaAlF6 Crystals Reviewed

    Masanori Koshimizu, Takayuki Yanagida, Yutaka Fujimoto, Atsushi Yamazaki, Kenichi Watanabe, Akira Uritani, Kentaro Fukuda, Noriaki Kawaguchi, Shunji Kishimoto, and Keisuke Asai

    Applied Physics Express   Vol. 6   page: 062061-1 - 062061-3   2013.5

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    The origin of the fast scintillation component of Ce-doped LiCaAlF6 crystal excited by gamma ray irradiation was studied with X-ray and vacuum
    ultraviolet (VUV) irradiation. A fast luminescence component was observed under VUV irradiation and was ascribed to luminescence at defects in
    the host matrix on the basis of VUV spectroscopy. No fast scintillation component was observed in the scintillation time profile under X-ray
    irradiation. The fast scintillation component under gamma ray irradiation can be concluded to be the result of Cherenkov radiation from energetic
    secondary electrons.

  92. Ce-doped LiF-SrF2 Eutectic Scintillators for Thermal Neutron Detection Produced at Different Solidification Rates Reviewed

    Takayuki Yanagida, Yutaka Fujimoto, Kentaro Fukuda, Noriaki Kawaguchi, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Valery Chani

    Optical Materials   Vol. 35 ( 7 ) page: 1449-1454   2013.5

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  93. Study on Background Gamma-Ray Reduction Using a Compton Backscattering Coincidence Technique

    Takashi Takagi, Kenichi Watanabe, Atsushi Yamazaki, and Akira Uritani

    IEEE TRANSACTIONS ON NUCLEAR SCIENCE   Vol. 60 ( 2 ) page: 550-554   2013.4

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  94. Temperature Dependence of Neutron-Gamma Discrimination Based on Pulse Shape Discrimination Technique in a Ce:LiCaAlF6 Scintillator

    Kenichi Watanabe, Yoshiyuki Kondo, Atsushi Yamazaki, Akira Uritani, Tetsuo Iguchi, Noriaki Kawaguchi, Kentaro Fukuda, Sumito Ishidu, Takayuki Yanagida, Yutaka Fujimoto, and Akira Yoshikawa

    IEEE TRANSACTIONS ON NUCLEAR SCIENCE   Vol. 60 ( 2 ) page: 959-962   2013.4

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  95. Two-dimensional Differential Calibration Method for a Neutron Dosimeter Using a Thermal Neutron Beam Reviewed

    Matsumoto, Tetsuro; Harano, Hideki; Masuda, Akihiko; Nishiyama, Jun; Matsue, Hideaki; Uritani, Akira; Nunomiya, Tomoya

      Vol. 155 ( 4 ) page: 505-511   2013.3

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    DOI: 10.1093/rpd/nct029

  96. Eu-doped 6LiF-SrF2 Eutectic Scintillators for Neutron Detection Reviewed

    Takayuki Yanagida, Kentaro Fukuda, Yutaka Fujimoto, Noriaki Kawaguchi, Shunsuke Kurosawa, Atsushi Yamazaki, Kenichi Watanabe, Yoshisuke Futami, Yuui Yokota, Jan Pejchal, Akira Yoshikawa, Akira Uritani, Tetsuo Iguchi

      Vol. 34 ( 5 ) page: 868-871   2012.3

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  97. Ultrafast Transparent Ceramic Scintillators Using the Yb3+ Charge Transfer Luminescence in RE2O3 Host Reviewed

    Takayuki Yanagida, Yutaka Fujimoto, Shunsuke Kurosawa, Kenichi Watanabe, Hideki Yagi, Takagimi Yanagitani, Vitezslav Jary, Yoshisuke Futami, Yuui Yokota, Akira Yoshikawa, Akira Uritani, Tetsuo Iguchi, and Martin Nikl

    Applied Physics Express 4 (2011) 126402   Vol. 4   page: 126402-126404   2011.12

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    We report a new discovery of Yb3+-doped ultrafast scintillators based on the Yb3+ charge transfer luminescence. Transparent ceramic Yb3+-doped Y2O3, Sc2O3, Lu2O3, and Yb2O3 were prepared by sintering. When irradiated by γ- and X-rays, they showed a well detectable photoabsorption peak in the pulse height spectra and ultrafast scintillation decay dominated by the decay time of about 1 ns. For the first time, the Yb3+-doped oxide materials show detectable scintillation in the pulse height measurement at room temperature with ultrafast scintillation decay.

  98. Feasibility Study on a Micro-Size Dosimeter Using an Optical Fiber Probe Based on a Photostimulable Phosphorescence Reviewed

    Kotaro Nakahashi, Kenichi Watanabe, Akira Uritani, Atsushi Yamazaki, Eiji Ariga

    Radiation Measurement   Vol. 46 ( 12 ) page: 1547-1550   2011.12

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    We propose a novel micro-size dosimeter using an optical fiber probe based on the PSL from the BaFBr:Eu2þ. Through basic experiments using the prototype dosimeter, the feasibility of the proposed dose monitoring method has been confirmed.We confirmthat increasing the stimulus laser poweris effective to improve the signal to noise ratio. The lower limit of detectable dose of the prototype dosimeter probe having sensitive region with the diameter of 200 mm is preliminarily estimated to be 11 mGy for a Co-60 gamma-rays. This value is much smaller than the typical irradiation dose (a few Gy per treatment) in the radiotherapy.We can measure the dose in a few hundred subdivisions during a treatment. We, therefore, conclude that the
    proposed micro-size dosimeter can be a promising candidate of in-vivo and on-line dose monitor in the
    radiotherapy.

  99. Development of Novel Rare Earth Doped Fluoride and Oxide Scintillators for Two-Dimensional Imaging Reviewed

      Vol. 29 ( 12 ) page: 1178-1182   2011.12

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    Two topics were focused. The first one was about the gamma-ray scintillator, Pr3+:Lu3Al5O12 (LuAG). The second one was about neutron scintillator, Ce3+:6LiCaAlF6 and Eu2+:6LiCaAlF6 (6LiCAF). Those scintillators have been developed very recently for modern imaging applications in the medical and homeland security fields. In both cases, the rare earth ions are playing the crucial role as emission centers. Pr3+ in LuAG provided fast 5d→4f transition providing noticeably shorter decay time than that of Ce3+. Among several candidate hosts, LuAG showed the best performance. Bulk crystal growth, basic scintillation properties, two-dimensional gamma-ray imaging and positron emission mammography (PEM) application were demonstrated. Due to the international situation, the homeland security was compromized by illicit traffic of explosives, drugs, nuclear materials, etc. and the ways to its improvement became an important R&D topic. For this purpose the Ce and Eu doped LiCAF appeared competitive candidates. Especially, when substitution of 3He neutron detectors was considered, the discrimination ability of gamma-ray from alpha-ray was important. Bulk crystal growth, basic scintillation properties and two-dimensional neutron imaging were demonstrated.

  100. Development of Neutron Diagnostic Systems for LHD Deuterium Experiments

    T. Iguchi, A. Uritani, N. Nishio, J. Kawarabayashi, K. Watanabe, A. Yamazaki, H. Tomita, M. Sasao, A. Okamoto, S. Kitajima, K. Ishii, T. Nishitani, K. Ochiai, M. Ishikawa, K. Shinihara, J. H. Kaneko, F. Fujita, H. Harano, T. Matsumoto, E. Takada, M. Isobe, T. Tanaka, K. Nishimura, H. Yamanishi and M. Osakabe

    Annual report of National Institute of Fusion Science     page: 219   2011.11

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  101. Study on Measurement of Total Neutron Yield during Deuterium Experiments and its Calibration

    A. Uritani, N. Nishio, J. Yamazaki, K. Watanabe, H. Yamanishi and M. Isobe

    Annual report of National Institute of Fusion Science     page: 108   2011.11

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  102. A Study on Electron Density Imaging Using the Compton Scattered X-ray CT Technique Reviewed

    Ryota Masuji, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani

    Nuclear Instruments and Methods in Physics Research Section A   Vol. 652 ( 1 ) page: 620-624   2011.10

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    We propose a novel electron density imaging technique based on a Compton scattered X-ray CT (CSX-CT)
    technique. We design fundamental configuration of the CSX-CT system, which consists of a fan-shaped
    X-ray beam, two-dimensional sensors for scattered X-ray detection, parallel plate collimators for limitation of the direction of scattered X-rays and a line sensor for the transmission of X-ray CT
    (TX-CT). An image obtained by the TX-CT can be used to correct the attenuation effect of scattered X-rays.
    Through Monte Carlo simulation modeling studies of the CSX-CT system, we demonstrate that the
    utilization of the information of scattered X-rays is useful to obtain the electron density image. We
    additionally confirm that the medical exposure irradiated in the CSX-CT is estimated to be lower than the maximum dose recommended in the guideline of some committees.

  103. Neutron-Gamma Discrimination Based on Pulse Shape Discrimination in a Ce:LiCaAlF6 Scintillator Reviewed

    Atsushi Yamazaki, Kenichi Watanabe, Akira Uritani, Tetsuo Iguchi, Noriaki Kawaguchi, Takayuki Yanagida, Yutaka Fujimoto, Yuui Yokota, Kei Kamada, Kentaro Fukuda, Toshihisa Suyama, Akira Yoshikawa

    Nuclear Instruments and Methods in Physics Research Section A Associated Equipment   Vol. 652 ( 1 ) page: 435-438   2011.10

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    We demonstrate neutron-gamma discrimination based on a pulse shape discrimination method in a Ce:LiCAF scintillator. We have tried neutron-gamma discrimination using a difference in the pulse shape or the decay time of the scintillation light pulse. The decay time is converted into the rise time through an integrating circuit. A 252Cf enclosed in a polyethylene container is used as the source of thermal neutrons and prompt gamma-rays. Obvious separation of neutron and gamma-ray events is achieved using the information of the rise time of the scintillation light pulse. In the separated neutron spectrum, the gamma-ray events are effectively suppressed with little loss of neutron events. The pulse shape discrimination is confirmed to be useful to detect neutrons with the Ce:LiCAF scintillator under an intense high-energy gamma-ray condition.

  104. Development of a Gamma-Camera with a Functional Collimator Reviewed

    Kenichi Watanabe, Junichi Sugiyama, Atsushi Yamazaki, Akira Uritani

    Nuclear Instruments and Methods in Physics Research Section AAssociated Equipment   Vol. 652 ( 1 ) page: 582-586   2011.10

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  105. Development of a Compact Flat Response Neutron Detector Reviewed

    H. Harano, T. Matsumoto, J. Nishiyama, A. Masuda, A. Uritani, K. Kudo

      Vol. 58 ( 5 ) page: 2421-2425   2011.10

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    Long counters are widely used as neutron fluence monitors for their flat response. However, a bulky neutron moderator is required to achieve the flat response, which can be a disadvantage for portability and an undesirable source of scattered neutrons. Reducing the size of the moderator degrades the flat response, especially for high-energy neutrons. We propose a new method to reduce the size of the moderator while keeping a flat response, and we develop a compact flat-response neutron detector. The detector consists of two small spherical $^{3}$ He proportional counters embedded at appropriate positions in a compact cylindrical polyethylene moderator. The sensitivity ratio between the two counters was adjusted to provide a flat response in the total outputs from the two counters. We demonstrated by MCNPX calculations and response measurements for Cf and Am-Be neutrons and monoenergetic neutrons that the present detector had a sensitivity comparable to long counters with a good flat response in a wide energy range up to 20 MeV while being only one-fifth of the weight of long counters. The positions of the effective center were determined as a function of neutron energy. We also proposed a method to evaluate the neutron energy using the detector, which will allow various new applications taking advantage of the ability to measure neutron fluence and energy at the same time.

    DOI: 10.1109/TNS.2011.2163191

  106. Flat-response Neutron Detector Using Spatial Distribution of Thermal Neutrons in a Moderator Reviewed

    Kenichi Watanabe, Junpei Otsuka, Musashi Shigeyama, Yousuke Suzuki, Atsushi Yamazaki, Akira Uritani

    Nuclear Instruments and Methods in Physics Research Section A   Vol. 652 ( 1 ) page: 392-396   2011.10

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    We propose a novel neutron detector that realized flat-response using information of a spatial
    distribution of thermal neutrons in a moderator. The proposed detector consists of a 3He position sensitive proportional counter(PSPC) and a cylindrical moderator surrounding the 3He PSPC. The
    cylindrical detector is irradiated by neutrons along the cylinder axis. The spatial response of the 3He
    PSPC is used to correct the detector response in to flat-response. We adopt a weighting method to
    achieve flat-response, in which detected neutrons weighted depending on their detected positions are
    accumulated as the detector response. Through Monte Carlo simulation studies, we confirm that the
    flat-response neutron detector can be realized by correcting the response of the proposed detector
    using the weights determined by a multiple least squar emethod (MLSM). Additionally, fundamental
    property of the 3He PSPC is experimentally investigated to check applicability to the proposed flat-response neutron detector. We conclude that we should take account of the end effect when
    determining the weights and correcting the detector response.

  107. Europium and Sodium Codoped LiCaAlF6 Scintillator for Neutron Detection Reviewed

    Takayuki Yanagida, Akihiro Yamaji, Noriaki Kawaguchi, Yutaka Fujimoto, Kentaro Fukuda, Shunsuke Kurosawa, Atsushi Yamazaki, Kenichi Watanabe, Yoshisuke Futami, Yuui Yokota, Akira Uritani, Tetsuo Iguchi, Akira Yoshikawa, and Martin Nikl

    Applied Physics Express 4 (2011) 126402   Vol. 4   page: 106401-106403   2011.9

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  108. Study on the Calibration of LHD Neutron Monitoring System Reviewed

    Naoto Nishio, Atsushi Yamazaki, Kenichi Watanabe, Akira Uritani, Mitsutaka Isobe and Hirokuni Yamanishi

    Plasma and Fusion Research   Vol. 6   page: 2405115-1 - 2405115-4   2011.8

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    Neutron monitoring is quite important because neutron yield generated by fusion reactions corresponds to
    the fusion output. In design of the neutron monitor, Monte Carlo simulations play an important role to make
    corrections on various parameters, such as neutron energy spectrum and spatial distribution when determining the calibration constant. We consider the calibration procedures using a Cf point source toroidally rotating in the vacuum vessel, and evaluate uncertainties of the calibration constant for the neutron detector placed on the center
    axis.

  109. Basic Study of Europium Doped LiCaAlF6 Scintillator and its Capability for Thermal Neutron Imaging Application Reviewed

    Takayuki Yanagida, Noriaki Kawaguchi, Yutaka Fujimoto, Kentaro Fukuda, Yuui Yokota, Atsushi Yamazaki, Kenichi Watanabe, Jan Pejchal, Akira Uritani, Tetsuo Iguchi and Akira Yoshikawa

      Vol. 33 ( 8 ) page: 1243-1247   2011.6

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  110. New Idea of a Small-Sized Neutron Detector with a Plastic Fibre Reviewed

    Tetsuro Matsumoto, Hideki Harano, Akihiko Masuda, Jun Nishiyama, Yoshinori Sakurai and Akira Uritani

    Radiation Protection Dosimetry   Vol. 146 ( 1-3 ) page: 92-95   2011.4

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  111. Absolute Measurement of Activity of 198Au Foils Using the 4πβ–γ Coincidence Counting Method and Corrections by the Monte Carlo Simulation Reviewed

    Jun Nishiyama, Hideki Harano, Tetsuro Matsumoto, Yasushi Sato, Akira Uritani and Katsuhisa Kudo

    Radiation Protection Dosimetry     page: 1-5   2011.3

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  112. Recent Activities on Neutron Standardization in Japan

    Hideki HARANO, Tetsuro MATSUMOTO, Jun NISHIYAMA, Akihiko MASUDA, Akira URITANI, Katsuhisa KUDO

    Progress in NUCLEAR SCIENCE and TECHNOLOGY   Vol. 1   page: 138-141   2011

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  113. Thermal Neutron Calibration Method Using an Intense Neutron Beam from JRR-3M Reviewed

    T. Matsumoto, H. Harano, J. Nishiyama, H. Matsue, A. Masuda, A. Uritani and K. Kudo

    Radiation Measurements   Vol. 45 ( 10 ) page: 1124-1126   2010.12

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    We have developed a thermal neutron calibration method using a reactor produced neutron beam in JRR-3M of the Japan Atomic Energy Agency. Neutron-induced prompt gamma ray analysis has usually been performed in this beam line. Neutron energy distributions with negligible contributions from epithermal neutrons were measured by a time-of-flight method with a chopper made of 6LiF powder. The thermal neutron flux was determined by a gold foil activation method. We found that the thermal neutron beam in JRR-3M was well suited for calibration, neutron detector development or neutron dosimetry.

  114. A Study on the Neutron Monitoring System of LHD Based on Monte Carlo Simulations Reviewed

    N. Nishio, S. Yamamoto, K. Watanabe, A. Uritani, M. Isobe, and H. Yamanishi

    Review of Scientific Instruments   Vol. 81   page: 10D-306-1-10D-306-3   2010.10

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    Neutron monitoring is quite important because fusion neutrons are a direct evidence of fusion reactions. In calibration experiments of a neutron monitoring system, Monte Carlo calculations play an important role to correct various effects. To perform Monte Carlo calculations for a helical type fusion device, we make a program that can automatically generate an input file of a helical coil geometry for the MCNP code. The neutron spatial distributions and spectra for the helical devices are calculated in the geometries automatically generated by this program. We also discuss in calibration experiments.

  115. Fusion Product Diagnostics Planned for Large Helical DeviceDeuterium Experiment Reviewed

    M. Isobe, H. Yamanishi, M. Osakabe, H. Miyake, H. Tomita, K. Watanabe, H. Iwai, Y. Nomura, N. Nishio, K. Ishii, J. H. Kaneko, J. Kawarabayashi, E. Takada, A. Uritani, M. Sasao, T. Iguchi, Y. Takeiri and H. Yamada

    Review of Scientific Instruments   Vol. 81   page: 10D-310-1-10D-310-5   2010.10

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    Deuterium experiment on the Large Helical Device LHD is now being planned at the National Institute for Fusion Science. The fusion product diagnostics systems currently considered for installation on LHD are described in this paper. The systems will include a time-resolved neutron yield monitor based on neutron gas counters, a time-integrated neutron yield monitor based on activation techniques, a multicollimator scintillation detector array for diagnosing spatial distribution of neutron emission rate, 2.5 MeV neutron spectrometer, 14 MeV neutron counter, and prompt -ray diagnostics.

  116. 中性子測定器の校正技術 Invited

    松本哲郎、原野英樹、工藤勝久、瓜谷章

    放射線   Vol. 34 ( 2 ) page: 101-109   2008.4

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  117. 中性子標準のトレーサビリティーと国際相互比較 Invited

    原野英樹、松本哲郎、工藤勝久、瓜谷章

    放射線   Vol. 34 ( 2 ) page: 111-115   2008.4

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  118. Development of the Fast Neutron Standard Using a Be(α,n) Reaction at the National Metrology Institute of Japan Reviewed

    T. Shimoyama, H. Harano, T. Matsumoto, K. Moriyama, T. Hata, K. Kudo, T. Koyamada, and A. Uritani

    Radiation Protection and Dosimetry   Vol. 126   page: 130-133   2007.8

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  119. Characterization of Kilo Electron Volt Neutron Fluence Standard with the 45Sc(p,n)45Ti Reaction at NMIJ Reviewed

    T. Matsumoto, H. Harano, T. Shimoyama, K. Kudo, and A. Uritani

    Radiation Protection and Dosimetry   Vol. 126   page: 155-158   2007.8

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    We are developing a national standard of a monoenergetic kilo electron volt neutron field with the 45Sc(p,n)45Ti resonance reaction. A wide resonance yields 27.4 keV neutrons at 0° with respect to the proton beam. The proton energy was precisely determined in the measurement of the relative neutron yield as a function of the proton energy from the threshold energy to 2.942 MeV. Absolute measurement of the monoenergetic neutron fluence was performed using a 3He proportional counter. Relative measurement was also carried out using a Bonner sphere calibrated at our 144 keV standard neutron field. Calibration factors were obtained between the count of a neutron monitor and the neutron fluence. A silicon-surface barrier detector with a 6LiF foil converter was also being developed for the neutron fluence measurement. Successful results were obtained in the tests in the 144 keV standard neutron field.

  120. International Key Comparison of Neutron Fluence Measurements in Mono-energetic Neutron Fields: CCRI(III)-K10 Invited Reviewed

    J Chen, Z Wang, C Rong, G L&ouml;vestam, A Plompen, N Puglisi, D M Gilliam, C M Eisenhauer, J S Nico, M S Dewey, K Kudo, A Uritani, H Harano, N Takeda, D J Thomas, N J Roberts, A Bennett, P Kolkowski, N N Moisseev, I A Kharitonov, S Guldbakke, H Klein

    Metrologia   Vol. 44   page: 58   2007

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    CCRI Section III (neutron measurements) conducted a unique key comparison of neutron fluence measurements in mono-energetic neutron fields. In contrast to former comparisons, here the fluence measurements were performed with the participants' instruments in the same neutron fields at the PTB accelerator facility. Seven laboratories - the CIAE (China), IRMM (EC), NMIJ (Japan), NIST (USA), NPL (UK), PTB (Germany) and the VNIIM (Russia) - employed their primary standard reference methods or transfer instruments carefully calibrated against their primary standards, to determine the fluence of 0.144 MeV, 1.2 MeV, 5.0 MeV and 14.8 MeV neutrons and reported calibration coefficients for a selected neutron monitor and each neutron energy with a detailed uncertainty budget for the measurements. The key comparison reference values (KCRV) were finally evaluated as the weighted mean values of the neutron fluence at 1 m distance from the target in vacuum per neutron monitor count. The uncertainties of each KCRV amounted to about 1%. The degree of equivalence (DoE), defined as the deviation of the result reported by the laboratories for each energy from the corresponding KCRV, and the associated expanded uncertainty are also reported. The deviations between the results of two laboratories each with the corresponding expanded uncertainties complete the documentation of the degrees of equivalence.

  121. Convenient Method of Relative Calibration of the Neutron Source Emission Rate between Ddifferent Source Types Reviewed

    H.Harano, T.Matsumoto, T.Shimoyama,Y. Sato, A. Uritani, Y.Hino, K. Kudo, T.Michikawa

    Nuclear Science, IEEE Transactions on   Vol. 53 ( 3 ) page: 1413 - 1417   2006.6

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    Neutron source emission rates are determined by absolute or relative measurement. The relative measurement is performed by comparing between a sample source and a calibrated reference source of the same type. In this calibration, the energy spectra of the sample and reference sources should be identical, since normally there exists energy dependence in the response of neutron detectors. We propose a method of relative calibration of the neutron source emission rate between different source types and spectra. In the present method, a sample source or a calibrated reference source is located at the center of a graphite pile and thermal neutron flux at a special position is monitored and compared. We performed gold foil activation measurements at the NMIJ/AIST graphite pile and revealed that the thermal neutron flux at that position per unit source emission rate is independent of the types of neutron sources. The details of the physical mechanism were examined by calculating the spectral fluence of the neutrons thermalized inside the graphite pile using the MCNP4C code. We demonstrated this method using Am-Be, Ra(α)-Be, Cf, Pu-Be neutron sources and obtained the successful results which agreed within 1%.

  122. Development of Dynamic Three-Dimensional Multi-Pinhole Gamma Camera Reviewed

    Hisato Takemoto, Kenichi Watanabe, Jun Kawarabayashi, Tetsuo Iguchi and Akira Uritani

      Vol. 43 ( 4 ) page: 344-347   2006.4

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    In this paper we propose a dynamic 3-D gamma camera consisting of multi-pinhole collimators and flat panel detectors. Through simulation studies on various pinhole configurations we determined that from a spatial and time resolution consideration, pinhole collimators with a 60° opening angle achieved acceptable dynamic 3-D imaging results. With regard to basic system performance, we estimated that the spatial and time resolution exceeds 3.5 mm and 4 s, respectively, for a small animal injected with 99mTc with an activity of 37 MBq. In addition, from further experiments we concluded that the proposed system would be acceptable and practical as a dynamic 3-D imager for nuclear medicine applications although position calibration concerns require further study.

  123. Improvement of Photon Collection Uniformity from an NE213 Scintillator Using a Light Guide Reviewed

    H.Harano, T.Matsumoto, Y.Shibata, Y. Ito, A.Uritani, K.Kudo

    Nuclear Science, IEEE Transactions on   Vol. 52 ( 6 ) page: 3147 - 3150   2005.12

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    The uniformity in collecting scintillation photons to the photomultiplier is one of the key parameters to carry out precise measurement using scintillators. A simple method is proposed to improve the collection uniformity of the scintillation photons just by inserting a light guide between a scintillator and a photomultiplier where the sidewall of the light guide is surrounded by a black paper as a photon absorber. This light guide insertion is expected to have a function to reduce the collection efficiency of the scintillation photons generated closer to the photomultiplier due to the larger transmission loss, since a decrease of the angle of incidence raises the fraction of the photons escaping from the sidewall of the light guide. The experiments using an NE213 liquid organic scintillation detector and gamma-ray sources revealed that the light guide functioned as a compensator for the original tendency of the photon collection and improved the photon collection uniformity. The details of the physical mechanism were examined by simulating the behavior of the gamma rays using the EGS4 electron-photon transport Monte Carlo code and the light propagation process using the ray-tracing program GuideM. The effects of the light guide were also examined on the whole energy resolution and the discrimination capability to separate gamma rays and neutrons.

  124. Fast Neutron Spectrometer Composed of PSPCs and Si(Li)-SSDs with Excellent Energy Rresolution and Detection Efficiency Reviewed

    T.Matsumoto, H. Harano, A. Uritani, K.Kudo

    IEEE Transactions on Nuclear Science   Vol. 52 ( 6 ) page: 2923 - 2926   2005.12

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    We have developed a fast neutron spectrometer composed of three position-sensitive proportional counters (PSPCs) with methane gas and two Si(Li) surface barrier semiconductor detectors (SSDs). A collimated incident neutron beam interacts with hydrogen atoms in the methane gas to generate recoil protons. Position information of the recoil protons obtained from the PSPCs gives the recoil angle. At the same time, the energy of the recoil protons is measured with the three PSPCs and the two SSDs. Finally, the neutron energy is derived using the recoil-proton energy and the recoil angle. This spectrometer was experimentally tested using a monoenergetic neutron beam with energy of 5.0 MeV. The energy resolution and the detection efficiency were 3.5% and 1.1 times10-3 %, respectively. The energy resolution could be achieved better than 2% by selecting events under proper conditions. We also developed a Monte Carlo code to evaluate the characteristics of the spectrometer. The results obtained from these simulations are compared to those obtained through experiments.

  125. 中性子検出器の開発動向 ―スペクトロメータを中心に―

    瓜谷 章

    放射線   Vol. 31 ( 4 ) page: 273-278   2005.10

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  126. Development of Compact Compton Gamma Camera for Non-destructive Detection and Location of Hidden Explosives with Neutron Induced Prompt Gamma-Ray Imaging

    T. Iguchi, J. Kawarabayashi, K. Watanabe, H. Kenjyo, A. Uritani

    Nuclear Science Symposium Conference Record, 2005 IEEE   Vol. 2   page: 735 - 739   2005.10

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    As a unique gamma-ray sensor for detection and location of hidden explosives with neutron induced prompt gamma-ray analysis, we are developing a compact and efficient Compton gamma camera based on stacked BGO scintillator rods to deduce the incident direction of characteristic 10.8 MeV gamma-rays produced from nitrogen abundant in explosives through neutron capture reaction. The detector unit consists of 5.4 mm times; 5.4 mm times 150 mm BGO scintillator rods stacked into an 8times8 array and two multi-anode photomultiplier tubes mounted at the both ends, which can measure three-dimensional position and intensity of scintillations produced through Compton multiple scattering inside the detector and follow the track of scattered gamma-rays backward according to Compton scattering kinematics to estimate the location of a specific energy gamma-ray source without any mechanical collimation. We have designed and constructed the prototype system of 6 detector units with multi-functional ASIC for multichannel signal read-out. The outline and applicability of this system is presented with some preliminary performance tests by using quasi-monochromatic 10.8 MeV gamma-ray beams produced through laser-Compton scattering with the electron storage ring.

  127. Convenient Method of Relative Calibration of the Neutron Source Emission Rate between Ddifferent Source Types

    H. Harano, T. Matsumoto, T. Shimoyama, Y. Sato, A. Uritani, Y. Hino, K. Kudo, T. Michikawa

    Nuclear Science Symposium Conference Record, 2005 IEEE   Vol. 1   page: 524 - 528   2005.10

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    Neutron source emission rates are determined by absolute or relative measurement. The relative measurement is performed by comparing between a sample source and a calibrated reference source of the same type. In this calibration, the energy spectra of the sample and reference sources should be identical, since normally there exists energy dependence in the response of neutron detectors. We propose a method of relative calibration of the neutron source emission rate between different source types and spectra. In the present method, a sample source or a calibrated reference source is located at the center of a graphite pile and thermal neutron flux at a special position is monitored and compared. We performed gold foil activation measurements at the NMIJ/AIST graphite pile and revealed that the thermal neutron flux at that position per unit source emission rate is independent on the types of neutron sources. The details of the physical mechanism were examined by calculating the spectral fluence of the neutrons thermalized inside the graphite pile using the MCNP4C code. We demonstrated this method using Am-Be, Ra(alpha)-Be, Cf, Pu-Be neutron sources and obtained the successful results which agreed within 1%.

  128. Development of a Novel Small-Sized Neutron Detector Based on a 6Li-Glass Scintillator

    T. Matsumoto, H. Harano, T. Shimoyama, A. Uritani, Y. Sakurai, K. Kudo

    Nuclear Science Symposium Conference Record, 2005 IEEE   Vol. 3   page: 1291 - 1293   2005.10

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    A small-sized thermal neutron detector based on a 6Li-glass scintillator and a plastic optical fiber was developed for measurement of a dose distribution of thermal neutrons in a thermal-neutron standard field. A contribution of gamma rays can not completely be neglected in the neutron measurement with this detector, although the 6Li-glass scintillator is distinguishable for the neutrons and the gamma rays by difference of each pulse height. Moreover, to reduce an uncertainty of neutron counts caused by the gamma ray background around a discrimination level, we suggested a gamma-ray suppression type of a small-sized thermal neutron detector with a 6Li-glass scintillator, a hollow CsI(Tl) scintillator and plastic optical fibers. The detector can reject signals due to the gamma rays with an anti-coincidence method. In the present paper, we evaluated the gamma-ray suppression ability of the detector using the EGS4 electron-photon transport Monte-Carlo code with the PRESTA routine. As the results, the sufficient gamma-ray suppression effect was shown.

  129. トレーサブルな中性子計測と国際比較 Invited

    工藤勝久、瓜谷章、原野英樹、松本哲郎、 戸田泰弘

    放射線   Vol. 31 ( 2 ) page: 105-110   2005.4

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    国際度量衡局が主催して行った単色エネルギー中性子フルエンスの国際比較について述べた。本論文では144keVと5.0MeVの2点について紹介しているが、日本の中性子フルエンス標準が、他国のそれと同等性を有していることを示した。

  130. Fast Neutron Spectrometer Composed of Position-Sensitive Proportional Counters and Si(Li)-SSDs with Excellent Energy Resolution and Detection Efficiency

    Progress Report   Vol. 194/U   page: 91   2005.3

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  131. Development of Real-time Thermal Neutron Monitor Using Boron-Loaded Plastic Scintillator with Optical Fiber for Boron Neutron Capture Therapy Reviewed

    M. Ishikawa, K. Ono, Y. Sakurai, H. Unesaki, A. Uritani, G. Bengua, T. Kobayashi, K. Tanaka ,T. Kosako

    Applied Radiation and Isotopes   Vol. 61 ( 5 ) page: 775-779   2004.11

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    A new thermal neutron monitor for boron neutron capture therapy was developed in this study. We called this monitor equipped boron-loaded plastic scintillator that uses optical fiber for signal transmission as an [scintillator with optical fiber] SOF detector. A water phantom experiment was performed to verify how the SOF detector compared with conventional method of measuring thermal neutron fluence. Measurements with a single SOF detector yielded indistinguishable signals for thermal neutrons and gamma rays. To account for the gamma ray contribution in the signal recorded by the SOF detector, a paired SOF detector system was employed. This was composed of an SOF detector with boron-loaded scintillator and an SOF detector with a boron-free scintillator. The difference between the recorded counts of these paired SOF detectors was used as the measure of the gamma ray contribution in the measured neutron fluence. The paired SOF detectors were ascertained to be effective in measuring thermal neutron flux in the range above 106 (n/cm2/s).

  132. Development of a Tiny Neutron Probe with an Optical Fiber for BNCT

    KURRI Progress Report 2003     page: 133   2004.10

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  133. Fast Neutron Spectrometer Composed of Position-Sensitive Proportional Counters and Si(Li)-SSDs with Excellent Energy Resolution and Detection Efficiency

    T. Matsumoto, H. Harano, A. Uritani, K. Kudo

    Nuclear Science Symposium Conference Record, 2004 IEEE   Vol. 2   page: 715 - 719   2004.10

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    We have developed a fast neutron spectrometer composed of three position-sensitive proportional counters (PSPCs) with methane gas and two Si(Li) detectors. A collimated incident neutron interacts with a hydrogen atom in the methane gas to generate a recoil proton. Position information on the recoil proton obtained from the PSPCs gives the recoil angle. At the same time, the energy of the recoil proton is measured with the three PSPCs and the Si(Li) detectors. Finally, the neutron energy is derived using the recoil-proton energy and the recoil angle. This spectrometer was experimentally tested using a monoenergetic neutron beam with energy of 5.0 MeV. The energy resolution and the detection efficiency were 3.5% and 1.1×10-5, respectively. The energy resolution better than 2% could be achieved by selecting events under proper conditions. We also developed a Monte-Carlo code in order to evaluate the characteristics of the spectrometer. The calculation results were compared with the experimental ones.

  134. Improvement of Photon Collection Uniformity from an NE213 Scintillator Using a Light Guide

    H. Harano, T. Matsumoto, Y. Shibata, Y. Ito, A. Uritani, K. Kudo

    Nuclear Science Symposium Conference Record, 2004 IEEE   Vol. 2   page: 841 - 845   2004.10

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    The uniformity in collecting scintillation photons to the photomultiplier is one of the key parameters to carry out precise measurement using scintillators. A simple method is proposed to improve the collection uniformity of the scintillation photons just by inserting a light guide between a scintillator and a photomultiplier where the sidewall of the light guide is surrounded by a black paper as a photon absorber. This light guide insertion is expected to have a function to reduce the collection efficiency of the scintillation photons generated closer to the photomultiplier due to the larger transmission loss, since a decrease of the angle of incidence raises the fraction of the photons escaping from the sidewall of the light guide. The experiments using an NE213 liquid organic scintillation detector and gamma-ray sources revealed that the light guide functioned as a compensator for the original tendency of the photon collection and improved the photon collection uniformity. The details of the physical mechanism were examined by simulating the behavior of the gamma rays using the EGS4 electron-photon transport Monte-Carlo code and the light propagation process using the ray-tracing program GuideM. The effects of the light guide were also examined on the whole energy resolution and the discrimination capability to separate gamma rays and neutrons.

  135. Construction of 144, 565 keV and 5.0 MeV Monoenergetic Neutron Calibration Fields at JAERI Reviewed

    Y. Tanimura, M. Yoshizawa, J. Saegusa, S. shimizu, M. Yoshida, Y. shibata, A Uritani, K Kudo

    Radiat Protection and Dosimetry   Vol. 110   page: 85-89   2004.9

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    Monoenergetic neutron calibration fields of 144, 565 keV and 5.0 MeV have been developed at the Facility of Radiation Standards of JAERI using a 4 MV Pelletron accelerator. The 7Li(p,n)7Be and 2H(d,n)3He reactions are employed for neutron production. The neutron energy was measured by the time-of-flight method with a liquid scintillation detector and calculated with the MCNP-ANT code. A long counter is employed as a neutron monitor because of the flat response. The monitor is set up where the influence of inscattered neutrons from devices and their supporting materials at a calibration point is as small as possible. The calibration coefficients from the monitor counts to the neutron fluence at a calibration point were obtained from the reference fluence measured with the transfer instrument of the primary standard laboratory (AIST), a 24.13 cm Bonner sphere counter. The traceability of the fields to AIST was established through the calibration

  136. Development of a Tiny Neutron Pprobe with an Optical Fibre for BNCT Reviewed

    Y. Ito, G. Katano, H. Harano, T. Matsumoto, A. Uritani, K. Kudo, K. Kobayashi, T. Yoshimoto, Y. Sakurai, T. Kobayashi, and C. Mori

    Radiat Protection and Dosimetry   Vol. 110 ( 1-4 ) page: 619-622   2004.8

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  137. Characterization of Gamma Rays Existing in the NMIJ Standard Neutron Field Reviewed

    H. Harano, T. Matsumoto, Y. Ito, A. Uritani, and K. Kudo

    Radiat Protection and Dosimetry   Vol. 110 ( 1-4 ) page: 69-72   2004.8

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  138. Development of a Fast Neutron Spectrometer Composed of Silicon-SSD and Position-Sensitive Proportional Counters Reviewed

    T. Matsumoto, H. Harano, Y. Ito, A. Uritani, K. Emi, and K. Kudo

    Radiat Protection and Dosimetry   Vol. 110 ( 1-4 ) page: 223-226   2004.8

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    A new fast neutron spectrometer has been developed. The spectrometer is composed of a silicon surface barrier detector and three position-sensitive proportional counters with methane gas working as counting gas and a radiator. A collimated incident neutron interacts with a hydrogen atom in the methane gas to generate a recoil proton. The position information on the path of the recoil proton obtained from the three position-sensitive proportional counters gives the recoil angle. In the meanwhile, the energy of the recoil protons is measured with the three proportional counters and the silicon surface barrier detector. The characteristics of the spectrometer were evaluated with a monoenergetic neutron beam. The best energy resolution was 1.8% for 5.0 MeV neutrons.

    DOI: 10.1093/rpd/nch125

  139. 産総研電子蓄積リングTERASの現状

    後神 進史、豊川 弘之、小池 正記、渡辺 一寿、座間 達也、池浦 広美、齋藤 則生、粟津 浩一、瓜谷 章、鈴木 功、齋藤 輝文

        page: 203-205   2004.8

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    産総研の電子蓄積リングTERASは760MeVの定常運転による放射光の他に、円偏光放射光やレーザー逆コンプトンγ線源としても利用されている。TERASにおいて、ここ一年間に行ったKickerやRF等の機器改良による蓄積電流量の向上、電子ビーム安定化、放射光利用環境の改善点、及び放射光利用による各研究成果等について報告する。

  140. イメージングプレートとマルチピンホールコリメータを用いた3次元ガンマカメラ

    瓜谷 章

      ( 597 ) page: 2-5   2004.1

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  141. Ideal Response Function of a 3He Proportional Counter to Thermal Neutrons Determined by Different Length Counters Reviewed

    K. Kudo, N. Takeda, A. Uritani, S. Koshikawa, Y. Shibata, K. Kobayashi and T. Yoshimoto

    Nucl. Instr. and Methods   Vol. B213   page: 305-309   2004.1

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    The gas multiplication distributions along the anode wires of 3He proportional counters with different sensitive lengths of 10, 15 and 20 cm were measured using a collimated thermal neutron beam at the Kyoto University Reactor facility. The ideal response function excluding the effect of electric field distortion near the boundaries of the anode wire was derived by taking into account the difference between pulse height spectra measured by two different length counters. The pulse height spectrum calculated by the NRESPG Monte Carlo code assuming the ideal gas multiplication region showed relatively good agreement with the response function derived from the measurements. Both the energy resolution of the full energy peak at 764 keV and the peak ratio to the entire pulse height spectrum were improved markedly.

  142. Photodisintegration of Deuterium and Big Bang Nucleosynthesis Reviewed

    K. Y. Hara, H. Utsunomiya, S. Goka, H. akimune, T. Yamagata, M. Ohta, H. Toyokawa, K. Kudo, A. Uritani, Y. Shibata, Y.-W. Lui, H. Ohgaki

    Physical Review D   Vol. 68 ( 7 ) page: 072001-1-072001-6   2003.10

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  143. Characterization of a Thermal Neutron Field at the Heavy Water Neutron Irradiation Facility of the Kyoto University Reactor (II)

    KURRI Progress Report 2002     page: 129   2003.10

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  144. New Position Sensitive Cryogenic Detector with Single Electron Transistor

    J. Kawarabayashi, K. Aoki, T. Kadoi, K. Watanabe, A. Uritani, T. Iguchi

    Nuclear Science Symposium Conference Record, 2003 IEEE   Vol. 2   page: 1355 - 1357   2003.10

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    We proposed a new micro-calorimetric detector with four single electron transistor (SET) read-out circuits that aimed the real-time detector with spatial resolution of 100 nm. The new detector consists of two layers of the micro-calorimeters. The top layer had four SETs, which worked as thermometers to decide the photoelectron position by the difference of each SET's temperature caused by heat flow in the layer. We investigated the SET performance and the heat flow in the substrate at cryogenic temperature. From calculational results, the temperature resolution of 10 mK could be achieved with a pico-ammeter having 5.0 × 10-9S sensitivity. Also, the detector configuration achieving the 100 nm spatial and 8 μ second time resolution was successfully designed.

  145. Characterization of a Thermal Neutron Field at the Heavy Water neutron Irradiation Facility of the Kyoto University Reactor

    A. Uritani, C. H. Pyeon, K. Kudo, K. Kobayashi, T. Yoshimoto, Y. Sakurai, T. kobayashi and C. Mori

    Proc. of 11th Inter. Conf. on Reactor Dosimetry     page: 340-344   2003.8

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  146. Development of Three-Dimensional Gamma Camera with Imaging Plates and Multi-Pinhole Collimators Reviewed

    Naofumi Yamamura, Akira Uritani, Kenichi Watanabe, Jun Kawarabayashi and Tetsuo Iguchi

    Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment   Vol. A505 ( 1-2 ) page: 577-581   2003.6

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    We have developed a novel multi-pinhole-type gamma camera for imaging low-energy gamma-ray emitters. The gamma camera consists of Imaging Plates (IPs) and multi-pinhole collimators made of a lead plate with many pinholes in lattice arrangement. The three-dimensional spatial distribution of a gamma-ray source is reconstructed by using a stereoscopic back-projection technique, where the directions of gamma-ray incidence are determined with the digitized two-dimensional images on the IPs and the configuration of the multi-pinhole collimators. The horizontal and vertical spatial resolutions for a point-like 57Co source evaluated with simulations are 1.5 and 2.5 mm, respectively.

  147. Characterization of a Thermal Neutron Field at the Heavy Water Neutron Irradiation Facility of the Kyoto University Reactor

    Japanese Nuclear data Committee, Progress Report   Vol. INDC(JPN) ( 190/U ) page: 59-62   2003.3

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  148. 産総研シングルエンド・イオン加速器4MeV(ペレトロン4UH-HC)の現状

    西島 俊二、武田直人、小倉 政彦、瓜谷 章、工藤 勝久

    第15回タンデム加速器及びその周辺技術の研究会     page: 21-24   2003.3

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    設置以来使用してきた稼動心臓部でもあるチャージング用ペレット・チェーンのナイロン部品の劣化による事故などを懸念していたが、予算面から4年越しで少しずつ買い揃えて4本分のチェーンが揃ったので昨年5月に交換に至った。当所の加速器は直流ビーム電流150μA (H+ Beam)の大電流仕様であり、4本のチャージング・チェーンを持っている。 今回の報告は、チャージング・チェーン交換に伴うトラブル発生と加速器のエネルギー安定性について報告する。

  149. 通常光ファイバーを用いた強放射線分布センシング法の開発

    河原林順、水野良治、中亮太郎、瓜谷 章、渡辺賢一、井口哲夫、辻村憲雄

    サイクル機構技報   ( 17 ) page: 97-107   2002.12

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    常のプラスチック光ファイバーにおいても放射線との相互作用で微弱シンチレーション光が発生することに着目し、これを用いることにより測定可能距離を大幅に延ばすとともに、その低検出効率を逆に活かして、より高フラックス下における放射線分布測定への適用可能性を検討した。その結果、これまでのシンチレーションファイバーを用いた場合に比べ、測定可能距離を約二桁のばすことできた。また、原子炉周辺や加速器、核融合実験装置環境等における放射線モニタリングへの適用の可能性を示した。また、ファイバー出力に対する分光学的片側読み出し手法を新規に考案し、その基本原理の有効性を実証した。

  150. 複眼式コリメータとイメージングプレートを用いた3次元ガンマカメラの開発

    瓜谷章、山村直史、田渕明、渡辺賢一、井口哲夫

      Vol. 17 ( 8 ) page: 71   2002.8

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  151. 高エネルギー加速器研究機構における黒鉛パイル熱中性子校正場の開発

    米内俊祐、佐波俊哉、佐々木慎一、中村尚司、道川太一、瓜谷章

    保健物理   Vol. 37 ( 2 ) page: 118-127   2002.6

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  152. Characterization of a Thermal Neutron Field at the Heavy Water Neutron Irradiation Facility of the Kyoto University Reactor

    Japanese Nuclear data Committee, Progress Report   Vol. INDC(JPN) ( 189(U) ) page: 65-33   2002.3

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  153. レーザー共鳴イオン化質量分析法を用いた極微量同位体分析における4重極質量分析器の適用性

    服部和裕,渡辺賢一,河原林順,井口哲夫,瓜谷章

    放射線   Vol. 28 ( 1 ) page: 55-60   2002.1

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  154. Radiation Distribution Sensing with Normal Optical Fiber Reviewed

    R. Naka, J. Kawarabayashi, K. Watanabe, A. Uritani, T. Iguchi, N. Hayashi, N. Kojima, T. Yoshida, J. Kaneko, H. Takeuchi, T. Kakuta

    IEEE Transactions on Nuclear Science   Vol. 48 ( 6 ) page: 2348-2351   2001.12

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    The purpose of this study is to develop a radiation distribution monitor using a normal plastic optical fiber. The monitor has a long operating length and can obtain continuous radiation distributions. A principle of the position sensing is based on a time-of-flight technique. The monitor is sensitive to beta rays or charged particles, gamma rays, and fast neutrons. The spatial resolutions for beta-rays ( 90Sr-90Y), gamma-rays (137Cs), and D-T neutrons are 30, 37, and 13 cm, respectively. The detection efficiencies for the beta-rays, gamma-rays, and D-T neutrons are 0.11%, 1.6×10 -5% and 1.2×10-4%, respectively. The effective attenuation length of the detection efficiency is 18 m. In this paper, we describe the basic characteristics of this monitor.

  155. Development of Failed Fuel Detection and Location Technique Using Resonance Ionization Mass Spectrometry Reviewed

    K. Watanabe, T. Iguchi, T. Ogita, A. Uritani and H. Harano

    Journal of Nuclear Science and Technology   Vol. 38 ( 10 ) page: 844-849   2001.10

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  156. Digital Waveform Analysis for 3He Ion Chamber Reviewed

    J. Kawarabayashi, M. P. Mardiyanto, A. Uritani and T. Iguchi, Nagoya University; J. Kaneko and H. Takeuchi

    IEEE Transactions on Nuclear Science   Vol. 48 ( 3 ) page: 527-529   2001.6

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    Numerical analyzes on individual pulses from a cylindrical 3 He gas ionization chamber have been performed. A radial distribution of the electron ion pairs was successfully analyzed by a deconvolution technique combined with a digital waveform analysis. From the charge distribution, clear separation of events of the reactions of 3He(n,p)T and 3He(n,n)3He at the energy region of the 3He recoil edge was observed.

  157. Energy Spectrum Improvement Based on Eucledian Distance with Digital-Analog Fusion Method Reviewed

    M.P. Mardiyanto, A. Uritani, J. Kawarabayashi, and T. Iguchi

    Journal of Nuclear Science and Technology   Vol. 38 ( 5 ) page: 301-305   2001.5

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    The application of a `digital-analog hybrid signal processing system' combined with a Euclidian distance method is presented. The proposed method is used to improve gamma-ray energy spectrum characteristics of a CdZnTe semiconductor detector. A digital and an analog system are simultaneously applied to the detector output after passing through a preamplifier, where the digital system digitizes the signal pulse shape for the Euclidian distance determination, while the analog system measures the signal pulse height with a conventional analog method. In this paper, the digital and the analog data are combined to improve the energy spectrum characteristics; giving the increase of the photopeak area, the peak-to-valley ratio, and the photopeak sharpness.

  158. Pulse Shape Analysis on Mixed Beta Particle and Gamma-ray Source Measures by CdZnTe Semiconductor Detector by Means of Digital-Analog Fusion Method Reviewed

    M.P. Mardiyanto, A. Uritani, J. Kawarabayashi, T. Iguchi, and H. Sakai

    Journal of Nuclear Science and Technology   Vol. 38 ( 5 ) page: 306-311   2001.5

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    We present a study on pulse shapes of a CdZnTe semiconductor detector for beta particles and gamma-rays emitted by a 137Cs-90Sr mixed source. When beta and gamma radiations enter a semiconductor detector, two kinds of pulses are produced according to the type of radiations. The characteristics of the pulses are determined by their energy and depth of interaction. The energy deposited on the detector basically determines the pulse height and the depth of interaction affects the pulse shape. Because of the different characteristics of beta and gamma radiations, their pulse shapes are also different. The digital-analog hybrid signal processing method was applied to separation of the beta spectrum from the beta-gamma mixed one. The separation of beta spectrum was done based on a neural network algorithm, a leading edge area method, and a falling continuum tail value method. However, the perfect separation could not be obtained. The separation was also done by reconstructing the spectra on the basis of subtraction of gamma-ray component. The spectra of beta particles and gamma-rays from 137Cs-90Sr mixed source could be separated well by using the reconstruction method.

  159. Pulse Shape Analysis Based on Similarity with Digital-Analog Fusion Method Reviewed

    M.P. Mardiyanto, A. Uritani, H. Sakai, J. Kawarabayashi, and T. Iguchi

    Nucl. Instr. and Methods   Vol. A462 ( 3 ) page: 405-410   2001.4

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  160. Conceptual Design of Compact Neutron Camera with Directional Neutron Detector for Nuclear Fusion Experimnt Reviewed

    T. Iguchi, T. Iizuka, A. Uritani and J. Kawarabayashi

    Fusion Technol.   Vol. 39 ( 2 ) page: 1147-1151   2001.3

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  161. Pulse Shape Analysis on Mixed Beta Particle and Gamma-ray Source Measured by CdZnTe Semiconductor Detector by Means of Digital-Analog Hybrid Signal Processing Method Reviewed

    M. Panitra Mardiyanto, A. Uritani, J. Kawarabayashi, T. Iguchi, H. Sakai

    Journal of Nuclear Science and Technology   Vol. 38 ( 5 ) page: 306-311   2001.3

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  162. Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER4/017

    B. Osmera, V. Lyssakov, F. Cvachvec, F. Hudec, B. Jansky, J. Mikus, E. Novak, S. Posta, Z. Turzik, M. Hort, V. Krysl||SKODA, V. Smutny, S. Zaritsky, N. Alekseev, M. Gurevitch, A. Egorov, E. Brodkin, K. Ilieva, S. Belousov, J. Kovbasenko, A. Uritani, T. Misawa, C. Mori

    ASTM/STP   Vol. 1398   page: 312-319   2001.2

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  163. A Novel Neutron Spectrometer with Response of Wide Energy Range

    ASTM/STP   Vol. 1398   page: 698-705   2001.2

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  164. Development of Neutron and Gamma-Ray Flux Distribution Measurement System with Scintillator and Optical Fiber Combination

    C. Mori, A. Uritani, T. Iguchi, S. Hayashi, Y. Takami, I. Kimura, M. Katagiri

    ASTM/STP   Vol. 1398   page: 769-774   2001.2

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  165. Simultaneous Measurement of Neutron Pulse Series in Time and Space by Using Position Sensitive Proportional Counter

    ASTM/STP   Vol. 1398   page: 811-818   2001.2

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  166. JT60Uにおける飛行時間型中性子スペクトロメータ

    柴田康成,井口哲夫,瓜谷章,河原林順,Magnus Hoek,西谷建夫,森岡篤彦

    放射線   Vol. 27 ( 1 ) page: 27-29   2001.1

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  167. Neutron Energy Spectrum Estimation Method with Information on Direction of Neutron Incidence at Spaceborne Neutron Monitor

    Y. Makihara, A. Uritani, T. Iguchi, J. Kawarabayashi, H. Toyokawa, N.Takeda, K. Kudo, S. Sato, S. Takagi, S. Iwai and C. Mori

    Proc. of 15th Workshop on Rsdistion Detectord and Their Uses   Vol. 2001 ( 20 ) page: 140-149   2001

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  168. Digital Waveform Analysis for 3He Ionization Chamber

    J. Kawarabayashi, M. P. Mardiyanto, A. Uritani, T. Iguchi, J. Kaneko, H. Takeuchi

    Nuclear Science Symposium Conference Record, 2000 IEEE   Vol. 2   page: 9/193 - 9/195   2000.10

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    Numerical analyses on individual pulses from a cylindrical 3 He gas ionization chamber have been performed. A radial distribution of the electron ion pairs was successfully analyzed by a deconvolution technique combined with a digital waveform analysis. From the charge distribution, clear separation of events of the reactions of 3He(n,p)T and 3He(n,n)3He at the energy range of the 3He recoil edge was observed.

  169. Radiation Distribution Sensing with Normal Optical Fiber

    R. Naka, J. Kawarabayashi, A. Uritani, T. Iguchi, J. Kaneko, H. Takeuchi, T. Kakuta

    Nuclear Science Symposium Conference Record, 2000 IEEE   Vol. 1   page: 6/231 - 6/234   2000.10

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    The purpose of this study is to develop a radiation distribution monitor using a normal plastic optical fiber. The monitor has a long operating length and can obtain continuous radiation distributions. A principle of;the position sensing is based on a time-of-flight technique. The monitor is sensitive to beta rays or charged particles, gamma rays, and fast neutrons. The spatial resolutions for beta rays ( 90Sr-90Y), gamma rays (137Cs) and D-T neutrons are 30 cm, 37 cm and 13 cm, respectively. The detection efficiencies for the beta rays, the gamma rays and D-T neutrons are 0.11%, 1.6×10-5% and 1.2×10-4%, respectively. The effective attenuation length of the detection efficiency is 18 m. In this paper, we describe the basic characteristics of this monitor.

  170. Development of Directional Neutron Detector for Compact Fast Neutron Camera

    T. Iguchi, S. Iizuka, A. Uritani, J. Kawarabayashi

    Nuclear Science Symposium Conference Record, 2000 IEEE   Vol. 1   page: 6/207 - 6/210   2000.10

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    A new concept of compact neutron camera with directional neutron detector arrays is proposed for nuclear fusion experiment. The basic performance of the directional neutron detector is made clear through experiment for a prototype detector with 14 MeV neutrons and design consideration of the detector specification to optimize its directionality. The results show that the angle resolution defined as a full width of neutron incident angles at a half maximum of detector counts would reach up to around 4 degrees at minimum around 45 degrees neutron incidence to the detector axis. The concept for a compact neutron camera is also given by making good use of an array of the optimized directional neutron detectors.

  171. Evaluation of Response Functions of 16"x16"x4" NaI Scintillation Detector for Environmental Gamma-ray Survey

    H. Itadzu, T. Iguchi, A. Uritani and J. Kawarabayashi

    Proceedings of the Second International Workshop on EGS     page: 250-254   2000.8

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  172. 円錐状突起電極型放射線画像検出器の開発

    寿山大介、河原林順、瓜谷章、井口哲夫

    放射線   Vol. 26 ( 2 ) page: 77-80   2000.4

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  173. 通常光ファイバーを用いた放射線分布センシングに関する基礎研究

    中亮太郎、河原林順、瓜谷章、井口哲夫、金子純一、竹内浩、角田恒巳

    放射線   Vol. 26 ( 2 ) page: 71-75   2000.4

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  174. Improvement of Energy Spectrum Characteristics of CdZnTe Semiconductor Detector with a Digital-analog Fusion Method Reviewed

    M.P. Mardiyanto, A. Uritani, H. Sakai, J. Kawarabayashi, and T. Iguchi

    Nucl. Instr. and Methods   Vol. A441 ( 3 ) page: 483-488   2000.3

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    We present a new application of a `Fusion Method' to improve gamma-ray energy spectrum characteristics of a CdZnTe semiconductor detector. A digital and an analog system are simultaneously applied for the detector output; The digital system digitizes the signal pulse shapes for pattern recognition based on a neural network algorithm. The analog measures the signal pulse heights with a conventional analog system. The digital and the analog output data are fused and then used for improvement of the energy spectrum characteristics, i.e. the photopeak area, the peak-to-valley ratio, and the FWHM of photopeaks.

  175. Pulse Shape Analysis Based on Similarity and Neural Network with Digital-Analog Fusion Method

    M.P. Mardiyanto, A. Uritani, H. Sakai, J. Kawarabayashi, and T. Iguchi

    Proc. 14th W. S. on Radiation Detectors and Their Uses, KEK Proc.   Vol. 2000   page: 132-141   2000

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  176. Development of Failed Fuel Detection and Location Technique Using Resonance Ionization Mass Spectrometry: Improvement of the Detection Limit with Pulsed Supersonic Valve

    Kenichi Watanabe, Tetsuo Iguchi, Toshiyuki Ogita, Takeshi Watanabe, Akira Uritani, Jun Kawarabayashi, Hideki Harano and Shoichi Nose

    Proc. 14th W. S. on Radiation Detectors and Their Uses, KEK Proc.   Vol. 2000 ( 14 ) page: 183-190   2000

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  177. Neutron/Proton Discrimination Characteristics of Spaceborne Neutron Monitors,

    Y. Makihara, A. Uritani, T. Iguchi, J. Kawarabayashi, H. Toyokawa, Y. Uwamino, O. Sato, S. Takagi, S. Iwai and C. Mori

    Proc. 14th W. S. on Radiation Detectors and Their Uses, KEK Proc   Vol. 2000 ( 14 ) page: 155-162   2000

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  178. Pulse Shape Recognition for CdZnTe Semiconductor Detector by using Multi-shaping Amplifiers Method with Neural Network Algorithm Reviewed

    H. Sakai, A. Uritani, C. Mori and T. Iguchi

    IEEE Trans. Nuclear Science   Vol. NS-46 ( 4 ) page: 806-809   1999.8

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    A new pulse shape recognition method with multi-shaping amplifiers, combined with a neural network algorithm, has been developed, where four pulse heights are sampled from one signal pulse through four linear amplifiers with different shaping time constants. The four pulse heights are used as characteristic parameters to recognize the pulse shape with a neural network. This method has been applied to signal processing for a CdZnTe semiconductor detector to improve the deteriorated energy spectra caused by pulse height deficits due to the different mobilities of electrons and holes in the detector. The neural network recognizes the pulse shape patterns and provides the corrective magnification factors of the pulse heights. After the corrective procedure, the energy spectrum for 137Cs gamma-rays is improved from 9.3 keV to 7.4 keV in the energy resolution (FWHM) of the 662 keV gamma rays photopeak. The photopeak becomes a considerably symmetrical shape without a low-energy tail. It has been verified that this method is simple and useful for pulse shape analyses, which can be used for many other applications.

  179. Measurement of the Thermal and Fast Neutron Flux in a Research Reactor with a Li and Th Loaded Optical Fibre Detector Reviewed

    Y. Yamane, A. Uritani, T. Misawa, J. K-H. Karlsson and I. Pazsit

    Nucl. Inst. and Methods   Vol. A432 ( 2-3 ) page: 403-409   1999.8

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    The spatial dependence of thermal and fast neutron flux was measured axially in the core of a 1 MW research reactor. The measurements were made by a thin optical fibre detector with a neutron sensitive ZnS(Ag) scintillation tip. For thermal neutrons 6Li was used, whereas for fast neutrons 232Th was used as neutron converter. The spatial dependence was measured by moving the fibre axially with a uniform speed. The measurement takes a few minutes, compared to up to 10 h with the conventional wire activation method. Comparison with traditional measurements shows a good agreement.

  180. 放射線検出器のニューラルネットワーク波形識別におけるデータ入力間隔の最適化

    酒井宏隆、瓜谷章、井口哲夫

    放射線   Vol. 25 ( 2 ) page: 115-122   1999.4

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  181. Spherical Neutron Detector for Space Neutron Measurement Reviewed

    S. Yamaguchi, A. Uritani, H. Sakai, C. Mori, T. Iguchi, H. Toyokawa, N. Takeda and K. Kudo

    Nucl. Instr. and Methods   Vol. A422 ( 1-3 ) page: 600-605   1999.2

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    A novel neutron detector has been developed to measure energy spectra of space neutrons in a spaceship. The detector consists of a spherical polyethylene moderator with a diameter of 30 cm and 19 pairs of 6Li- and 7Li-glass scintillators arranged along the orthogonal x-, y-, and z-axes of the sphere. The pairs can distinctively detect thermal neutrons in some radiation fields, where other radiation exists, by subtracting the number of detected events of the 7Li-glass scintillator from that of the 6Li-glass one. Hence the detector can clearly obtain the thermal neutron flux distribution in the spherical moderator even in such fields. The detector was applied to the measurement of monoenergetic and 252Cf neutrons. The characteristics of the detector were studied by comparison with the simulations.

  182. Time-Spatial Neasurement by Using Position-Sensitive 3He Proportional Counter

    Y. Kitamura, T. Misawa, H. Unesaki, S. Shiroya, A. Uritani and K. Ishitani

    Nucl. Instr. and Methods   Vol. A422 ( 1-3 ) page: 64-68   1999.2

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    Time-spatial neutron measurement was carried out by using a position-sensitive 3He proportional counter (PSPC) in the Kyoto University Critical Assembly. The data of the output pulses from the PSPC were acquired by a data acquisition system which was based on the LN-9000 system of Laboratory Equipment Corporation. In this system, the time and the position data of the neutron detection pulses were simultaneously accumulated by a personal computer. In the present study, the Rossi-α method, which was derived for time-domain neutron correlation analysis, was extended in order to process the measured two-dimensional data of time and space. The processed experimental results and a theoretical formula based on the one-group diffusion approximation neglecting the higher modes agreed well with each other, which indicates the present system is applicable for reactor physics experiments including reactor kinetics.

  183. High Energy Resolution Spectrometer with Propotrional Counter and Si-Detector Telescope Type for 14MeV Neutrons in Plasma Diagnostics Reviewed

    C. Mori, J. Goto, A. Uritani, H. Miyahara, Y. Ikeda, Y. Kasugai, J. Kaneko, M. Sasao, Y. Sakuma, K. Kudo and N. Takeda

    Nucl. Instr. and Methods   Vol. A422 ( 1-3 ) page: 75-78   1999.2

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  184. Measurement of Neutron and Gamma Ray Intensity Distributions with an Optical Fiber-Scintillator Detector

    C. Mori, A. Uritani, H. Miyahara, T. Iguchi, S. Shiroya, K. Kobayashi, E. Takada, R. F. Flemming, Y. K. Dewaraja, D. Stuenkel, G. F. Knoll

    Nucl. Instr. and Methods   Vol. A422 ( 1-3 ) page: 129-132   1999.2

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    On the tip of an optical fiber, a very small amount of ZnS(Ag) scintillator mixed with neutron converter and adhesive paste was painted, which can be inserted into a narrow space and moved by a fiber-driving unit controlled with a personal computer. The presented method made it possible to measure neutron flux distributions in critical assemblies, research reactors or other neutron facilities with position resolution of less than 1 mm and in 10 min or so over a meter. As neutron converter, 6Li and 235U are good for thermal neutrons and 232Th is useful for fast neutrons. When a neutron converter is not used, the method can be applied to the measurement of γ-ray intensity distribution.

  185. New Pulse Shape Analysis Method with Multi-shaping Amplifiers Reviewed

    H. Sakai, A. Uritani. K. Inoue, Y. Takenaka, C. Mori and T. Iguchi

    Nucl. Instr. and Methods.   Vol. A421 ( 1-2 ) page: 316-321   1999.1

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    A novel pulse-shape analysis method that uses similarity to recognize an individual pulse shape is presented in this paper. We obtain four pulse heights by using four linear amplifiers with different shaping time constants. We treat a combination of the four pulse heights as a pattern vector. A similarity of the pulse shape can be obtained by comparison between the pattern vector and a discriminant vector which was given in advance. Each pulse shape is analyzed by using the similarity. The method has been applied for the improvement of characteristics of a CdZnTe semiconductor detector. The characteristics of the energy spectrum of the CdZnTe detector such as the photopeak efficiency or the peak-to-valley ratio are improved after the correction procedure with the similarity.

  186. コンプトンカメラによるガンマ線イメージング

    瓜谷章

    放射線   Vol. 25 ( 1 ) page: 87-92   1999.1

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  187. 実践!放射線計測応用技術[6][原子炉分野]試験・研究炉、臨界装置、加速器炉

    森千鶴夫、瓜谷章

    原子力eye   Vol. 45 ( 6 ) page: 64-67   1999

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  188. Pulse Shape Recognition for CdZnTe Semiconductor Detector by Using Multi-shaping Amplifiers Method with Neural Network Algorithm

    H. Sakai, A. Uritani, C. Mori, T. Iguchi

    Nuclear Science Symposium Conference Record, 1999 IEEE   Vol. 1   page: 662 - 665   1998.10

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    A new pulse shape recognition method with multi-shaping amplifiers, combined with a neural network algorithm, has been developed, where four pulse heights are sampled from one signal pulse through four linear amplifiers with different shaping time constants. The four pulse heights are used as characteristic parameters to recognize the pulse shape with a neural network. This method has been applied to signal processing for a CdZnTe semiconductor detector to improve the deteriorated energy spectra caused by pulse height deficits due to the different mobilities of electrons and holes in the detector. The neural network recognizes the pulse shape patterns and provides the corrective magnification factors of the pulse heights. After the corrective procedure, the energy spectrum for 137Cs gamma-rays is improved from 9.3 keV to 7.4 keV in the energy resolution (FWHM) of the 662 keV gamma ray photopeak. The photopeak becomes a considerably symmetrical shape without a low-energy tail. It has been verified that this method is simple and useful for pulse shape analyses, which can be used for many other applications.

  189. Evaluation of Counting Loss and Its Correction for Small Pulses in the Internal Counting with Proportional Counters Reviewed

    C. Mori, Y. Wu, T. Agemura, A. Uritani, H.Miyahara, T. Suzuki and M. Yoshida

    International J. Applied Radiation and Isotopes   Vol. 49 ( 9-11 ) page: 1107-1111   1998.9

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    In the absolute radioactivity determination of gaseous samples using the internal gas counting method with proportional counters, evaluation of counting losses of pulses whose pulse heights are lower than the discrimination level is very important to obtain high accuracy. Counting losses due to wall effect and to very low energy of a β-ray were evaluated by experiment and EGS4 Monte Carlo calculation. The calculated results agreed well with experimental results when parameters in the EGS4 code were properly chosen; which shows the calculation code is able to be applied to other radioactive nuclides and other measurement conditions for the evaluation of counting losses.

  190. Novel Pulse Shape Analysis Method by Using Similarity Reviewed

    Y. Takenaka, A. Uritani , K. Inoue, H. Sakai and C. Mori

    International J. Applied Radiation and Isotopes   Vol. 49 ( 9-11 ) page: 1219-1223   1998.9

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    A novel pulse-shape-analysis method that uses the similarity of patterns to recognize individual pulse shapes is presented. The principle of this method is described. The method has been applied to improve the gamma-ray energy spectrum of a CdZnTe semiconductor detector. The energy spectrum has been improved with increased photopeak efficiency and better energy resolution.

  191. Improvement of Precision in Quantitative Measurement of Radioactivity with Imaging Plate Reviewed

    T. Suzuki, C. Mori, K. Yanagida, A. Uritani, H.Miyahara, M. Yoshida and F. Takahashi

    International J. Applied Radiation and Isotopes   Vol. 49 ( 9-11 ) page: 1127-1130   1998.9

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    To obtain a high precision in radiation or radioactivity measurements with an imaging plate, the photo-stimulated luminescence intensity must be large. To get the highest intensity, we reread an imaging plate repeatedly and summed each intensity for the purpose of reducing the variation of the measured intensities. A great improvement of the precision in the measurement was achieved with the method of repeated readings when the time interval between each reading is more than about 1 h.

  192. Measurement of Eigenvalue Separation by Using Position Sensitive Proportional Counter Reviewed

    K. Ishitani, Y. Yamane, A. Uritani, T. Iguchi and S. Shiroya

    Annals of Nuclear Energy   Vol. 25 ( 10 ) page: 721-732   1998.6

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    Eigenvalue separation is an important index of power reactor stability in the view of neutronics. In recent years, a long, slender Position Sensitive Proportional Counter has been developed. By using this proportional counter, the spatial neutron flux distribution of a nuclear reactor can be measured rapidly. Using these characteristics, we intend to develop the experimental method evaluating eigenvalue separation as an index for reactor stability. A method based on spatial integrals of neutron flux measured at a subcritical system with an external source is proposed. To verify this method, experiments were carried out at Kyoto University Critical Assembly. It was confirmed that eigenvalue separation can be evaluated within a relative error of 10%.

  193. 講座 放射線防護用機器 XVII. 放射線管理計測技術の最近の進歩 1.位置感応型検出器とその応用

    瓜谷章、飯田孝夫、森千鶴夫

      Vol. 47 ( 2 ) page: 155-165   1998

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  194. Pulse Shape Recognition with Neural Network Algorithm

    H. Sakai, A. Uritani, C. Mori and T. Iguchi

    Proceedings of the 12th Workshop on Radiation Detectors and Their Uses     page: 28-37   1998

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  195. Improvement of Energy Spectrum Characteristics of CdZnTe Semiconductor Detector by means of Digital Waveform Processing with neural network algorithm Reviewed

    H. Sakai, Y. Takenaka, A. Uritani, K. Inoue and C. Mori

    Nuclear Instruments and Methods   Vol. A400 ( 2-3 ) page: 401-408   1997.12

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    We have studied the improvement of gamma-ray energy spectrum characteristics of a CdZnTe semiconductor detector by means of a neural network algorithm. The neural network recognizes the pulse shapes and determines the corrective magnification factors of pulse heights. After the corrective procedure with the network, the gamma-ray energy spectra of some radioisotope sources become more ideal with better energy resolution.

  196. Performance of a Spherical Neutron Counter for Spectroscopy and Dosimetry Reviewed

    H. Toyokawa, M. Yoshizawa, A. Uritani, C. Mori, N. Takeda and K. Kudo

    IEEE transaction   Vol. NS-44 ( 3 ) page: 788-791   1997.6

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    A spherical neutron counter for spectroscopy and dosimetry has been developed. The counter consists of a spherical polyethylene moderator and three slender 3He position-sensitive proportional counters. Rough measurements of neutron fluence spectra and ambient dose equivalents, H*(10), have been done in the moderated-neutron field of JAERI. Characteristics of the counter are examined and compared with those of a Bonner sphere neutron spectrometer.

  197. An Electronically Collimated Gamma Camera with a Parallel Plate Collimator for Tc-99m Imaging Reviewed

    A. Uritani , N. H. Clinthorne, J. E. Gormley J. W LeBlanc, W L. Rogers, D. K. Wehe and S. J. Wilderman

    IEEE Transaction   Vol. NS-44 ( 3 ) page: 894-898   1997.6

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    We present a new idea to apply a parallel plate collimator to an electronically collimated gamma camera, to reduce the complexity of image reconstruction. Back projected images obtained experimentally and using Monte Carlo simulations are shown. Using the collimator, backprojected images of single low-energy gamma-ray emitters can be obtained with larger signal-to-noise ratio than those obtained without the collimator. The results show that this method is useful in obtaining Tc-99m images.

  198. Characteristics and Correction of the Fading of Imaging Plate Reviewed

    T. Suzuki, C. Mori, K. Yanagida, A. Uritani, H.Miyahara, M. Yoshida and F. Takahashi

    J. Nucl. Sci. Technol.   Vol. 34 ( 5 ) page: 461-465   1997.5

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    When the latent images formed by exposure with incident particles in the phosphor of Imaging Plate (IP) are irradiated with laser beam, photo-stimulated luminescence (PSL) is emitted and read through a photomultiplier. PSL intensity fades with increasing the elapsed time between the exposure and the PSL reading. When the IP is read successively, the PSL intensities decrease with the number of reading times. The tendency of the decreasing becomes gradual with increasing the elapsed time after exposure. The multiple successive reading method gives the means of the correction of the fading.

  199. Characteristics of Prompt Scintillation from Imaging Plate Reviewed

    T. Suzuki, C. Mori, K. Yanagida, A. Uritani, H.Miyahara, K. Takahashi, J. Miyahara, M. Yoshida and F. Takahashi

    Nucl. Instr. and Methods   Vol. A390 ( 1-2 ) page: 155-159   1997.5

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  200. A Spherical Neutron Counter with Extended-Energy Response for Dosimetry Reviewed

    H. Toyokawa, A. Uritani, C. Mori, N. Takeda and K. Kudo

    Radiation Protection Dosimetry   Vol. 70 ( 1-4 ) page: 365-370   1997.4

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  201. New Position Sensing Method for Position-sensitive Proportional Counter with Neural Network Algorithm Reviewed

    H. Sakai, A. Uritani, K. Inoue, Y. Takenaka and C. Mori

    Nucl. Instr. and Methods   Vol. A385 ( 2 ) page: 335-338   1997.1

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  202. Experimental and Calculational Evaluation of Energy Loss of Radiations in Radioisotope source and Nuclear Detector

    C. Mori, H. Sakai, N. Takeuchi, T. Genka, Y. Wu, A. Uritani and H. Miyahara

    Proc. the First International Workshop on EGS4     page: 206-214   1997

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  203. シンチレータ塗布・光ファイバーを用いた中性子束・γ線強度分布測定法の開発

    森千鶴夫、影山一巳、槙林康雄、瓜谷章、宮原洋、柳田勝男、井口哲夫、三澤毅、山根義宏、小林圭二、代谷誠治、市原千博、林正俊、宇根崎博信、木村逸郎、吉井康司、高田英治、中澤正治

    京都大学原子炉実験所第31回学術講演会報文集     page: 221-226   1997

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  204. Development of Fast Neutron Spectrometer of Proportional Counter and Si-Detector Telescope Type Reviewed

    C. Mori, M. Tojo, K. Yanagida, J. Goto, A. Uritani, H. Miyahara, Y. Wu, K. Kudo, N. Takeda, Y. Ikeda, Y. Kasugai, T. Iida, Y. Sakuma and M. Sasao

    Fusion Technology   Vol. 30 ( 3 ) page: 1134-1138   1996.12

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  205. 方向依存応答を示す新型中性子測定器の線源スペクトル推定逆問題への適用

    豊川弘之、瓜谷章、森千鶴夫、吉澤道夫、武田直人、工藤勝久

    放射線   Vol. 22 ( 4 ) page: 29-38   1996.11

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  206. Neutron Spectrometer with Position-Sensitive Proportional Counters Reviewed

    H. Toyokawa, A. Uritani, C. Mori, M. Yoshizawa, N. Takeda and K. Kudo

    Nucl. Instr. and Methods   Vol. A381 ( 2-3 ) page: 481-487   1996.11

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    A spherical neutron counter for spectrometry and dosimetry has been developed. The counter consists of a spherical polyethylene moderator and three slender 3He position-sensitive proportional counters inserted into the moderator. The thermal neutron distribution in the moderator, which is a function of the energy of the incident neutrons is obtained with the proportional counters. Characteristics of the counter have been studied with experiments and Monte Carlo simulations. Also shown are energy spectra of a 252Cf neutron source that are obtained by an unfolding method using the thermal neutron distributions as response functions.

  207. Performance of a Spherical Neutron Counter for Spectroscopy and Dosimetry

    H. Toyokawa, M. Yoshizawa, A. Uritani, C. Mori, N. Takeda, K. Kudo

    Nuclear Science Symposium Conference Record, 1996 IEEE   Vol. 2   page: 856 - 859   1996.10

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    A spherical neutron counter for spectroscopy and dosimetry has been developed. The counter consists of a spherical polyethylene moderator and three slender 3He position-sensitive proportional counters. Rough measurements of neutron fluence spectra and ambient dose equivalents, H*(10), has been done in the moderated-neutron field of JAERI. Characteristics of the counter are examined and compared with those of a Bonner sphere neutron spectrometer.

  208. An Electronically-Collimated Gamma Camera with a Parallel Plate Collimator for Tc-99m Imaging

    A. Uritani, N. H. Clinthorne, J. E. Gormley, J. W. LeBlanc, W. L. Rogers, D. K. Wehe, S. J. Wilderman

    Nuclear Science Symposium Conference Record, 1996 IEEE   Vol. 1   page: 287 - 291   1996.10

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    We present a new idea to apply a parallel plate collimator to an electronically-collimated gamma camera, to reduce the complexity of image reconstruction. Back projected images obtained experimentally and using Monte Carlo simulations are shown. Using the collimator, backprojected images of single low-energy gamma-ray emitters can be obtained with better spatial resolution and larger signal-to-noise ratio than those obtained without the collimator. The results show that this method is useful in obtaining Tc-99m images.

  209. 1-D Position Sensitive Single Carrier Semiconductor Detectors Reviewed

    Z. He, G. F. Knoll, D. K. Wehe, R. Rojeski, C. H. Mastrangelo, M. Hammig, C. Barrett, A. Uritani

    Nucl. Instr. and Methods   Vol. A380 ( 1-2 ) page: 228-231   1996.10

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    A single polarity charge sensing method has been studied using coplanar electrodes on 5 mm cubes of CdZnTe γ-ray detectors. This method can ameliorate the hole trapping problem of room-temperature semiconductor detectors. Our experimental results confirm that the energy resolution is dramatically improved compared with that obtained using the conventional readout method, but is still about an order of magnitude worse than the theoretical limit. A method to obtain the γ-ray interaction depth between the cathode and the anode is presented here. This technique could be used to correct for the electron trapping as a function of distance from the coplanar electrodes. Experimental results showed that a position resolution of about 0.9 mm FWHM at 122 keV can be obtained. These results will be of interest in the design of higher performance room-temperature semiconductor γ-ray detectors.

  210. Radioactivity Distribution Measurement of Various Natural Material Surfaces with Imaging Plate Reviewed

    C. Mori, T. Suzuki, S. Koido, A. Uritani, H.Miyahara, K. Yanagida, M. Yoshida and J. Miyahara

    J. of Radioanalytical and Nucl. Chem.   Vol. 206 ( 2 ) page: 263-268   1996.6

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  211. Improvement of Energy Resolution of CdTe Semiconductor Detector by Means of Digital Waveform Processing with Neural Network Algorithm Reviewed

    H. Sakai, A. Uritani, K. Inoue, Y. Takenaka and C. Mori

    J. of Radioanalytical and Nucl. Chem.   Vol. 205 ( 1 ) page: 147-155   1996.4

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  212. Effect of Background Radiation Shielding on Natural Radioactivity Distribution Measurement with Imaging Plate" Reviewed

    C. Mori, S. Koido, T. Suzuki, A. Uritani, H. Miyahara, K. Yanagida and J. Miyahara

    Nucl. Instr. and Methods   Vol. A369 ( 2-3 ) page: 544-546   1996.2

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    Distribution images of natural radioactivity contained in various natural materials such as vegetable, animal meat and pottery work can be obtained with an imaging plate which has high sensitivity for nuclear radiations. For such very low levels of radioactivity, natural background radiations must be reduced using a shielding box. The lining, on the inside of the box, with low atomic number material such as acrylic resin is very effective in reducing electrons, β-rays and low energy X- and γ-rays emitted from the inner surface of the shielding material. Some images of natural radioactivity distribution were obtained and the radioactivity, mainly 40K, contained in natural materials was measured by using an HPGe detector and also the imaging plate itself.

  213. Energy Resolution Enhancement of CdTe Semiconductor Detector Spectra by Using a Neural Network Algorithm Reviewed

    Y. Takenaka, A. Uritani, K. Inoue, H. Sakai, O. Kubota, H. Toyokawa and C. Mori

    Nucl. Instr. and Methods   Vol. A369 ( 2-3 ) page: 637-641   1996.2

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  214. Use of Natural Radioactivity Distribution Images of Vegetables at Public Meetings Reviewed

    C. Mori, S. Koido, T. Suzuki, H. Miyahara, A. Uritani, Y. Wu, K. Yanagida, M. Yoshida, F. Takahashi, J. Miyahara and K. Takahashi

    Proc. 10th Pacific Basin Nuclear Conference   ( 2 ) page: 921-925   1996

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  215. シンチレータ塗布・光ファイバーを用いた中性子束分布位置高分解能迅速測定法の開発(II)

    三戸祐一郎、森千鶴夫、影山一巳、柳田勝男、瓜谷章、宮原洋、小林圭二、市原千博、代谷誠治、宇根崎博信、木村逸郎

    京都大学原子炉実験所第30回学術講演会報文集     page: 219-224   1996

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  216. シンチレータ塗布・光ファイバーを用いたγ線強度分布測定法の開発

    影山一巳、森千鶴夫、三戸祐一郎、柳田勝男、瓜谷章、宮原洋、小林圭二、市原千博、代谷誠治、林正俊、宇根崎博信、木村逸郎

    京都大学原子炉実験所第30回学術講演会報文集     page: 225-228   1996

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  217. 球形滅速材と位置検出型比例計数管を用いた多目的中性子測定器の開発

    豊川弘之、瓜谷章、森千鶴夫

    放射線   Vol. 21 ( 4 ) page: 52-58   1995.10

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  218. 比例計数管と半導体検出器を組み合わせた速中性子エネルギースペクトロメーターの開発

    東條匡志、森千鶴夫、瓜谷章、豊川弘之、工藤勝久、武田直人

    放射線   Vol. 21 ( 4 ) page: 59-62   1995.10

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  219. A Multi-Purpose Spherical Neutron Counter Reviewed

    H. Toyokawa, A. Uritani, C. Mori. N. Takeda and K. Kudo

    IEEE Trans. on Nuclear Science   Vol. NS-42 ( 4 ) page: 644-648   1995.8

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    We have developed a unique neutron counter applicable to measurements of fluence, energy distribution and the dose equivalent of neutrons with very wide energy range, and to estimations of incident direction of neutron beams. This 4π sensitive neutron counter consists of a spherical polyethylene moderator and three charge-division-type position-sensitive proportional counters (PSPCs) inserted into the moderator orthogonally with each other. The three PSPCs give thermal neutron distributions in the spherical moderator that bring us the above information. The characteristics of this neutron counter have been studied with Monte Carlo simulations and with experiments using monoenergetic neutrons.

  220. Research for Application of Long Counter with a Position-Sensitive Proportional Counter to Neutron Dosimetry

    Reactor Dosimetry   Vol. STP1228   1995.8

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  221. A Long and Slender Position-Sensitive Helium-3 Proportional Counter with an Anode Wire Supported by a Ladder-Shaped Solid Insulator Reviewed

    A. Uritani, Y. Kuniya, Y. Takenaka, H. Toyokawa, Y Yamane, C. Mori, K. Kobayashi, S. Shiroya and C. Ichihara

    J. Nucl. Sci. Technol.   Vol. 32 ( 8 ) page: 719-726   1995.8

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    A long and slender position-sensitive 3He proportional counter with an outer diameter of 8mm and an effective length of 1.2m has been developed to measure neutron flux distributions in a critical assembly. Because it is difficult to make such a long and slender counter of con- ventional structure where an anode wire is stretched at the center of a cylindrical cathode tube, three prototype electrode systems of which anode wires are supported by insulator plates have been proposed. Among these three electrode systems, the electrode system of which anode wire is stuck on a ladder-shaped insulator has been adopted. The neutron flux distributions in the core of the Kyoto University Critical Assembly (KUCA) have been measured with the counter. Some non-uniformity of the detection efficiency has been observed throughout the counter. This non-uniformity has been corrected by calibrating the position-dependent detection efficiency with a gold wire activation method. A fairly satisfactory distribution, where the relative deviation from the gold wire activation method is 5.0%, has been obtained. Though the non-uniformity of the detection efficiency should be solved for precise measurements, the counter can be used for quick and rough measurements of neutron flux distributions.

  222. Application of Digital Waveform Processing to Position-Sensitive Proportional Counter Reviewed

    Y. Takenaka, A. Uritani and C. Mori

    J. Nuclear Science and Technology   Vol. 32 ( 4 ) page: 295-300   1995.4

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    In a charge-division type position-sensitive proportional counter (PSPC) with an anode wire of small resistance, a reflected component from an opposite end and thermal noise involved in signals deteriorate the position resolution of the PSPC. A digital waveform processing method was applied to the reduction of these undesirable effects by skillfully utilizing their signal characteristics that can be observed as inversely correlative signals between two-output signals from both sides of the PSPC. The digital waveform processing could improve the position resolution compared to a conventional pulse height processing method with analog filters. When the digital waveform processing was applied to signals of an equivalent circuit simulating the PSPC, the position resolutions defined by the full width at half maximum were improved to about 30% of those of conventional analog pulse processing. In the case of an actual PSPC, the position resolutions by the digital waveform processing were improved by 4-10% as compared with those of conventional pulse height processing.

  223. 中性子位置検出型核分裂計数管の開発

    森千鶴夫、安藤彰浩、瓜谷章、羽賀剛

    放射線   Vol. 21 ( 1 ) page: 35-42   1995.1

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  224. Characterization of Hexafluoroethane as Counting Gas of Position-Sensitive 3He Proportional Counter Reviewed

    A. Uritani and C. Mori

    Radioisotopes   Vol. 44 ( 1 ) page: 23-27   1995.1

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  225. シンチレータ塗布・光ファイバーを用いた中性子束分布・位置高分解能迅速測定法の開発

    森千鶴夫、三戸祐一郎、柳田勝男、影山一巳、国谷浩、瓜谷章、宮原洋、山根義宏、三澤毅、小林圭二、市原千博、代谷誠治、林正俊、宇根崎博信

    京都大学原子炉実験所第29回学術講演会報文集     page: 193-198   1995

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  226. Reduction of Microphonic Noise with Digital Waveform Processing Reviewed

    A. Uritani, O. Kubota Y Takenaka and C. Mori

    Nuclear Instruments and Methods   Vol. A351 ( 2-3 ) page: 598-599   1994.12

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    This paper describes a new method of microphonic noise reduction by digital waveform processing. This method predicts the microphonic noise shape over the duration of a detector signal by making full use of the periodicity of the noise, and then removes the microphonic noise component from the detector signal. Preliminary experimental results that prove the validity of this method are presented.

  227. Reduction of Digital Errors of Digital Charge Division Type position Sensitive Proportional Counter Reviewed

    A. Uritani, K. Yoshimura, Y. Takenaka and C. Mori

    Nuclear Instruments and Methods   Vol. A353 ( 1-3 ) page: 246-250   1994.12

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  228. Measurement of Radioactivity Distribution of Material Surfaces with Imaging Plate Reviewed

    C. Mori, T. Suzuki, S. Koido, H. Miyahara, A. Uritani, T. Aoyama and K. Nishizawa

    Nuclear Instruments and Methods   Vol. A353 ( 1-3 ) page: 371-374   1994.12

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  229. Dependence of Position Signal on Pressure of Counting Gas in Charge Division Type Position-Sensitive Proportional Counter Reviewed

    Y. Wu, C. Mori, A. Uritani, H. Miyahara, K. Yanagida and M. Yoshida

    J. Nuclear Science and Technology   Vol. 31 ( 11 ) page: 1194-1201   1994.11

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    In the absolute radioactivity measurement of radioisotope gaseous samples with newly developed position-sensitive proportional counter (PSPC) method, it is necessary to change the counting gas pressure for the correction of the wall effect. The position signal was found to drift depending on the pressure. Theoretical explanation was given for this drift. Rise time of output pulses varies with gas pressure, which leads to a change of ballistic deficit. Consequently, the ballistic deficit differs between pulses from both the ends of the PSPC, which causes the change of position signals. Increasing the pressure of the counting gas from 0.5×105Pa to 4×105Pa, the range of position signals for two position calibration sources became narrower by about 8% under 6μs shaping time.

  230. Reduction of Microphonic Noise by Digital Waveform Processing

    A. Uritani, O. Kubota, Y. Takenaka, C. Mori

    Nuclear Science Symposium Conference Record, 1994 IEEE   Vol. 1   page: 905 - 909   1994.10

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    This paper describes a new reduction method of microphonic noises, or some other periodic noises by means of digital waveform processing. This method predicts the microphonic noise shape over the duration of a detector signal by making full use of periodicity of the noise, and then removes the noise component from the detector signal. Experimental results that prove the validity of this method are presented.

  231. A Multipurpose Spherical Neutron Counter

    H. Toyokawa, A. Uritani, C. Mori, N. Takeda, K. Kudo

    Nuclear Science Symposium Conference Record, 1994 IEEE   Vol. 1   page: 968 - 972   1994.10

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    We have developed a unique neutron counter applicable to measurements of fluence, energy distribution and the dose equivalent of neutrons with a very wide energy range, and to estimations of the incident direction of neutron beams. This 4π sensitive neutron counter consists of a spherical polyethylene moderator and three charge-division-type position-sensitive proportional counters (PSPCs) inserted into the moderator orthogonally with each other. The three PSPCs give thermal neutron distributions in the spherical moderator that bring us the above information. The characteristics of this neutron counter have been studied with Monte Carlo simulations and with experiments using monoenergetic neutrons.

  232. A Study on Position Resolution of Position-Sensitive 3He Proportional Counter Reviewed

    A. Uritani, N. Marnada, Y. Takenaka, C. Mori and H. Miyahara

    Nuclear Instruments and Methods   Vol. A350 ( 1-2 ) page: 286-290   1994.10

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    The influences of wall effects and saturation of the gas multiplication on position resolutions of position-sensitive 3He proportional counters have been studied by means of numerical calculations, computer simulations and experiments. When the proton produced by the 3He(n,p)t reaction loses its specific energy in a counter wall by wall effects, a good position resolution is obtained escaping from any effects of a finite range of the proton and the triton. In the case where the gas multiplication is saturated, the best position resolution is obtained by selecting low pulse height events that the protons and the tritons move perpendicularly to the anode wire.

  233. Optimization of Counting Time in the Radioactivity Measurement of Gaseous Samples with Inner Counting Method Reviewed

    Y. Wu, C. Mori, A. Uritani, K. Yanagida, H. Miyahara, T. Aoyama and M. Yoshida

    Nuclear Instruments and Methods   Vol. A343 ( 2-3 ) page: 539-544   1994.4

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  234. Simple and Quick Measurement of Neutron Flux Distribution by Using an Optical Fiber with Scintillator Reviewed

    C. Mori, T. Osada, K. Yanagida, T. Aoyama, A. Uritani, H. Miyahara, Y. Yamane, K. Kobayashi, C. Ichihara and S. Shiroya

    J. Nuclear Science and Technology   Vol. 31 ( 3 ) page: 248-249   1994.3

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  235. Analytical Calculations on Radioactivity Measurements of 192Ir-Metallic Sources with a Calibrated Ionization Chamber Reviewed

    A. Uritani, T Genka, C. Mori and D. F. G. Reher

    Nuclear Instruments and Methods   Vol. A339 ( 1-2 ) page: 377-380   1994.1

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    The self-attenuation of photons was analytically calculated for an 192Ir metallic wire source and an aqueous standard source. The influence of the self-attenuation on the current of the calibrated ionization chamber was also evaluated. The self-attenuation did considerably affect the ionization current. It was concluded that the apparent radioactivity must be multiplied by a correction factor larger than unity (1.09±0.01 in the present case) to get the true radioactivity when the radioactivity of the 192Ir metallic wire source was measured with the ionization chamber calibrated with the aqueous standard source of 192Ir.

  236. Radioactivity Measurement of 192Ir Wire Sources with a Microcalorimeter Reviewed

    T. Genka, S. Iwamoto, N. Takeuchi, A. Uritani and C. Mori

    Nuclear Instruments and Methods   Vol. A339 ( 1-2 ) page: 398-401   1994.1

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    Radioactivities of metallic 192Ir sources are measured with a microcalorimeter nondestructively. In order to convert the complete decay energy evolved from the source into thermal energy, a tungsten block is used as radiation absorber. The sample sources measured are four thin wires of Ir/Pt alloy with dimensions of 0.1 mm&oslash; × 10 mm1, each coated by 0.1 mm thick platinum, giving the final diameter of 0.3 mm&oslash;. Overall uncertainty of the measurement for some 60 MBq activity is ±3.2%. Measurements of the wire sources with an ionisation chamber give smaller activities which are smaller by 10% than those from microcalorimetry mainly because of the autoattenuation effect.

  237. Direct Measurement of Gaseous Activities by Diffusion-in Long Proportional Counter Method Reviewed

    M. Yoshida, T. Yamamoto, Y. Wu, T. Aratani, A. Uritani

    Nuclear Instruments & Methods   Vol. A330 ( 1-2 ) page: 158-164   1993.6

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    Direct measurement of gaseous activities by the diffusion-in long proportional counter method (DLPC method) was studied. The measuring time without end effect was estimated by observing the behavior of 37Ar in the counter and was long enough to carry out the accurate activity measurement. The correction for wall effect was also examined on the basis of the measured and calculated correction factors. Among the tested gases of methane, P10 gas and propane, P10 gas was made clear to be a suitable counting gas for the DLPC method because of good diffusion properties and small wall effect. This method is quite effective for standardization of gaseous activities used for tracer experiments and calibration works of radioactive gas monitoring instruments.

  238. Application of Digital Waveform Processing to signals Acquired from Position-sensitive Detector

      Vol. 19 ( 2 ) page: 33-40   1993.5

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  239. Fabrication and Characteristics of a High Pressure Tiny Pump for Gas Circulation in Radioactivity Measurement of Gaseous Samples Reviewed

    Y. Wu, C. Mori, T. Yamamoto, K. Yanagida, A. Uritani, H. Miyahara, T Aoyama and M.

    Radioisotopes   Vol. 42 ( 4 ) page: 209-215   1993.4

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  240. 中性子位置検出器

    瓜谷 章

      Vol. 42 ( 9 ) page: 549-550   1993

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  241. Characteristics of a Position-Sensitive Fission Counter and Its Applications Reviewed

    C. Mori, A. Uritani, A. Ando, T. Osada, Y. Kuniya, K. Kobayashi, S. Shiroya, C. Ichihara

    Kyoto University Research Reactor Institute Progress Report     page: 140-141   1993

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  242. Radioactivity Measurement of 85Kr with Position -sensitive Proportional Counter Reviewed

    C. Mori, T Yamamoto, T Suzuki, A. Uritani, K. Yanagida, Y. Wu, T. Watanabe and M. Yoshida

    Nuclear Instrument & Methods   Vol. A312 ( 1-2 ) page: 189-192   1992.2

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    Direct radioactivity measurement of 85Kr is difficult with ionization chambers, since it emits high-energy β-rays (Eβmax = 667 keV) which results in a severe wall effect. Also with proportional counters, the end-effect must be taken into account. The position-sensitive proportional counter (PSPC) method which can eliminate the end-effect was applied to direct measurement of 85Kr radioactivity. In the measurement, logarithmic amplifiers were employed to clearly distinguish between β-ray signals and noise signals, and to eliminate digital error in the calculation of position information. The radioactivity of 85Kr was determined with ±0.80% standard deviation.

  243. Characteristics of a Position-Sensitive Fission Counter and Its Applications Reviewed

    C. Mori, A. Ando, A. Uritani, K. Yanagida, Y. Kuniya, C. Ichihara, S. Shiroya, K. Kobayashi

    Kyoto University Research Reactor Institute Progress Report     page: 138-139   1992

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  244. A New Position-sensitive Nuclear Fission Counter with a Convenient Read out Method for Neutron Measurement Reviewed

    C. Mori, T Haga and A. Uritani

    Nuclear Instrument & Methods   Vol. A310 ( 1-2 ) page: 437-440   1991.12

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  245. Measurement of Neutron Flux Distribution in Critical Assembly with Position-Sensitive Helium-3 Proportional Counter Reviewed

    A. Uritani, C. Mori, T Haga, K. Yanagida N. Marnada, K. Kobayashi, S. Shiroya and C. Ichihara

    J. Nuclear Science and Technology   Vol. 28 ( 9 ) page: 824-830   1991.9

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  246. Highly Reliable Low-level Neutron Detection Using 3He Proportional Counters Reviewed

    T. Aoyama, C. Mori, A. Uritani, T. Matsui and K. Naito

    Radioisotopes   Vol. 40 ( 5 ) page: 189-192   1991.5

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  247. Novel Position -sensing Method Using Fast and Slow components in the Output Signal from a Proportional counter Reviewed

    A. Uritani, C. Mori, T Watanabe and A. Miyahara

    Nuclea Instrument & Methods   Vol. A299 ( 1-3 ) page: 231-233   1990.12

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    We have developed a novel position-sensing method of a proportional counter using slow and fast components in the output signal observed at one end of a resistive anode wire of which the other end is grounded through a capacitor. This paper describes the principle of the position sensing and some experimental results. Fairly sufficient characteristics in position resolution and integral linearity were obtained. This method will extend the application field of position-sensitive detectors.

  248. Application of a Logarithmic Amplifier to a Charge-Division-Type Position-sensitive Proportional Counter Reviewed

    C. Mori, T Suzuki, A. Uritani, T Yamamoto, K. Yanagida, T Watanabe and M. Yoshida

    Nuclear Instrument & Methods   Vol. A299 ( 1-3 ) page: 128-132   1990.12

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    Fulfillment of both observation of pulses ranging from about 10 mV to 10 V through ADC and carrying out an arithmetic calculation with small digital errors for such digitized pulses is usually difficult, although it is required in measurements using a charge-division-type position-sensitive proportional counter (PSPC). However, the use of a logarithmic pulse amplifier sometimes solves this problem. The advantage of using a logarithmic pulse amplifier is described through the application of the amplifier to absolute-radioactivity measurements of gaseous samples and to the simultaneous measurement of geometrical distributions of neutrons and gamma-rays with the PSPC.

  249. Novel Position Sensing Method Using Fast and Slow Components in an Output Signal from a Proportional Counter Reviewed

    A. Uritani and C. Mori

    Nuclear Instruments and Methods   Vol. A294 ( 3 ) page: 677-678   1990.9

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    We propose a novel position-sensing method using slow and fast components in an output signal observed at one end of a resistive anode wire in a proportional counter in which the other end of the anode wire was grounded through a capacitor. Fairly sufficient characteristics in position resolution and an integral linearity were obtained. This method will extend the application field of a position-sensitive detector.

  250. Development of Position-Sensitive Helium-3 Proportional Counter for Thermal Neutrons with Novel Signal Readout Reviewed

    A. Uritani, C. Mori, T Watanabe and A. Miyahara

    J. Nuclear Science & Technology   Vol. 27 ( 8 ) page: 712-717   1990.8

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    A position sensitive 3He proportional counter for thermal neutrons with a novel signal readout method which has two pre-amplifiers at only one end of the counter body has been developed. It has an advantage for usage in a special environment, such as in a subcritical facility or in water, or for insertion into a narrow space. The characteristics of the counter were evaluated with thermal neutrons. The position resolution was 7 mm with an effective length of 1, 200 mm. The integral non-linearity of position signal was less than 0.5%.

  251. 熱中性子用位置検出型比例計数管の開発

    瓜谷章、森千鶴夫

    放射線   Vol. 16 ( 2 ) page: 80-91   1990.3

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  252. Improvement of Signal Readout in Charge Division Type Position Sensitive Proportional Counter Reviewed

    A. Uritani, C. Mori, T Watanabe and A. Miyahara

    J. Nuclear Science & Technology   Vol. 26 ( 12 ) page: 1094-1101   1989.12

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    It is generally difficult to insert a position sensitive proportional counter (PSPC) with a conventional charge division in a narrow space, or to work the counter under special environments, such as in water or in a reactor. We improved the position signal readout to make it possible to use a PSPC under such environments. A position signal was extracted from only one end of an anode wire by grounding the other end through a capacitor and a total charge signal was obtained from twelve cathode wires stretched parallel to the anode wire, so that two pre-amplifiers were able to be connected at only one end of the counter. The character-istics of the PSPC with the improved signal readout were examined with X-rays. The position resolution was 1.3 mm with an effective length of 550 mm, and depended on the X-ray injection position. A non-linearity of position signals was less than 0.2%.

  253. Multi element Position Sensitive Proportional Counter for Measurement of Tritium Labeled Gas Movement Reviewed

    C. Mori, A. Uritani and T. Watanabe

    J. Nuclear Science and Technology   Vol. 25 ( 4 ) page: 341-349   1988.4

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    A multielement position sensitive proportional counter was developed for the measurement of 3H labeled gas movement in a pipe by internal counting. The counter consists of an outer cylindrical pipe with an inner diameter of 40 mm, seven resistive stainless steel anode wires with a diameter of 22μm, and 24 cathode wires with a diameter of 120μm. These wires divide the radial cross section of the pipe into seven regions. Since each region independently works as a position sensitive proportional counter and the seven resistive anode wires are connected in series through lump resistors, the region and the axial position where a β-decay event occurred can be known by a simple operation upon the charge signals obtained from two preamplifiers. The axial position resolution for 3H β-rays was 9 mm FWHM. Demonstrative experiments were performed for the flow and diffusion of 3H labeled ethane in the counter pipe.

  254. Charge Transfer Process and Sputtering Process of Self-sustaining alkali Metal Coating on Metal Surface Reviewed

    A. R. Krauss, O. Auciello, A. Uritani, M. Valentine, R. Mendelsohn and D. M. Gruen

    Nuclear Instrument & Methods   Vol. B27 ( 1 ) page: 209-220   1987.6

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    It is well known that adsorption of electronegative or electropositive atoms on a metal surface results in charge transfer between the metal conduction band and the adsorbate atom. This charge transfer results in the formation of a coverage-dependent image dipole and a consequent change in the work function and adsorbate binding energy. Additionally, the secondary electron yield and the charge state of surface atoms desorbed by thermal, electron impact or ion impact desorption processes are closely related to the effective adsorbate charge.

    We discuss here the effect of Gibbsian segregation as a means of producing similar effects for electropositive (alkali metal) layers on a number of metal substrates. Classical chemisorption theory is used as a means of estimating the adsorbate effective charge and the results are compared with models used to predict the secondary ion fraction of sputtered atoms. The resulting concept of self-sustaining sputter-resistant coatings is analyzed in the context of applications to the fusion environment as well as to, e.g., materials for high current electrical contacts.

  255. New Partial Pressure Gauge for Helium and Deuterium Using the Ion Backscattering Principle Reviewed

    K. Akaishi, Y Kubota, A. Uritani and Y Hori

    J. Vacuum Science and Technology   Vol. A5 ( 4 ) page: 2444-2446   1987.6

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    A new partial pressure gauge is proposed that is capable of measuring partial pressures of He and D2 gases in the mixture. The gauge consists of a conventional ion scattering spectrometer with a Wien filter. The influence of the residual gases CH4 and H2O on the pressure measurements of D2 and He in this gauge is discussed.

  256. Implantation and Replacement of Hydrogen Isotopes Implanted in 304 Stainless Steel Vacuum Wall under RF Discharge and RF-DC Glow Discharge Reviewed

    K. Akaishi, Y Kubota, A. Uritani and Y Hori

    J. Nuclear Material   Vol. 145-147   page: 275-279   1987.2

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  257. Conceptual Design and Engineering Aspect of Tokamak Burning Plasma Experiments -the R-projects, Chapter 5 Vacuum System

    A. Uritani and K. Akaishi

    Nuclear Engineering Design/Fusion   Vol. 42 ( 2 ) page: 405-409   1987.1

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  258. R & D Efforts for the R-TOKAMAK Components

    A. Miyahara, Y. Fujii-e, K. Kamada, Y. Oka, O. Kaneko, K. Sakurai, T. Kuroda, K.N.Sato, A. Uritani, K. Akaishi and H. Amano

    Nuclear Engineering Design/Fusion   Vol. 42 ( 2 ) page: 357   1987.1

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    In parallel to the conceptual design of the R-tokamak, research and development efforts on
    the systems and the components have been carried out to obtain scopes to realize the device.
    Because we intended to introduce DT fuels into the device, the items of research and
    development works are quite different to that of non-burning machines. Alminium alloy
    developments to avoid activations by 14 MeV neutron irradiations, tritium safe handling and
    vacuum system with tritium are examples of this category. Beside specific requirement directly
    caused by DT introduction, highly reliable operation of the machine is strongly requested,
    because it is the necessary condition to perform experiments safely. However, these efforts are
    still in an early stage of investigation and many efforts are needed to prepare a rigid data base
    tokamak operation with reacting plasma.

  259. 高周波、直流グロー放電下における水素同位体の交換脱離

    赤石憲也、久保田雄輔、瓜谷章、堀洋一郎

    真空   Vol. 29 ( 5 ) page: 160-169   1986.5

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  260. イオン散乱法を用いた重水素、ヘリウム分圧の新らしい計測法

    瓜谷章、赤石憲也、久保田雄輔、堀洋一郎

    真空   Vol. 29 ( 5 ) page: 249-252   1986.5

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  261. A New Partial Pressure Gauge for He and D2 Using Ion Backscattering Technique Reviewed

    A. Uritani, K. Akaishi, Y. Kubota, Y. Hori and A. Miyahara

    Japanese J. Applied Physics   Vol. 25 ( 5 ) page: L403-L405   1986.5

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  262. イオン後方散乱法による重水素、ヘリウム分圧計測法

    瓜谷章、赤石憲也、久保田雄輔、堀洋一郎、宮原昭

    核融合研究   Vol. 55 ( 4 ) page: 360-370   1986.4

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  263. Charge Transfer Processes and Sputtering Processes of Self-Sustaining Alkali Metal Coating on Metal Surface

    A.R.Krauss, O.Auciello, A.Uritani, M.Valentine, R.Mendelsohn and D.M.Gruen

    US DOE Report   Vol. 860807 ( 2 ) page: 43-53   1986.1

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  264. 水素吸収におけるZr-V合金のISS観察

    瓜谷章、赤石古也、久保田雄輔、堀洋一郎、壁谷善三郎、鈴木基行、蒲生孝治

    真空   Vol. 28 ( 5 ) page: 317-320   1985.5

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  265. ポリイミドの水素透過係数の測定

    瓜谷章、赤石憲也、小川雄一、日野利彦、勝村広

    真空   Vol. 28 ( 5 ) page: 321-323   1985.5

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  266. Position-Sensitive Proportional Counter for Measurement of Tritium Labelled Gas Movement Reviewed

    C. Mori, M. Nakamoto, A. Uritani and T Watanabe

    J. Nuclear Science & Technology   Vol. 21 ( 12 ) page: 942-948   1984.12

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    A position sensitive proportional counter of a charge division type with a single resistive anode wire was constructed for the measurement of the movement of 3H labelled gas which is flowing or diffusing in a pipe. The introduction of resistors between the anode wire and pre-amplifiers brought a uniform detection efficiency for 3Hβ-rays throughout the counter. The position resolution was 3.1 mm FWHM. Detection efficiency was almost 100% uniformly over about 700 mm in the total anode length of 740 mm. The movement of 3H labelled gas could be measured effectively.

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Books 9

  1. 放射線と安全につきあう

    西澤邦秀、柴田理尋、瓜谷章・・・( Role: Contributor)

    名古屋大学出版会  2017.5  ( ISBN:978-4-8158-0875-4

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    Language:Japanese Book type:Scholarly book

  2. 原子力・量子・核融合事典

    多数( Role: Joint author)

    丸善出版  2014  ( ISBN:978-4-621-08874-6

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    Language:Japanese

  3. Reduction of Inter-Event Dead Time in Data Acquisition System for Simultaneous Measurement of Neutron Pulse Series in Time and Space

    Y. Kitamura, T. Misawa, H. Unesaki, S. Shiroya, K. Ishitani, A. Uritani and, Y. Yamane( Role: Joint author)

    Reactor Dosimetry  2001 

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    Language:English

  4. Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER4/017

    B. Osmera, V. Lyssakov, F. Cvachvec, F. Hudec, B. Jansky, J. Mikus, E. Novak, S. Posta, Z. Turzik, M. Hort, V. Krysl, V. Smutny, S. Zaritsky, N. Alekseev, M. Gurevic., A. Egorov, E. Brodkin, K. Ilieva, S. Belousov, J. Kovbasenko, A. Uritani, T. Misawa( Role: Joint author)

    Reactor Dosimetry  2001 

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    Language:English

  5. Development of Neutron and Gamma-Ray Flux Distribution Measurement System with Scintillator and Optical Fiber Combination

    C. Mori, K. Kageyama, Y. Mito, K. Yanagida, A. Uritani, H. Miyahara, Y. Wu, K. Kobayashi, C. Ichihara, S. Shiroya, M. Hayashi, H. Unesaki, I. Kimura, T. Iguchi and M. Nakazawa( Role: Joint author)

    Reactor Dosimetry  2001 

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    Language:English

  6. A Novel Neutron Spectrometer with Response of Wide Energy Range

    A. Uritani, S. Yamaguchi, Y. Makihara, J. Kawarabayashi, T. Iguchi, C. Mori, H. Toyokawa, N. Takeda, K. Kudo, S. Sato, S. Iwai( Role: Joint author)

    Reactor Dosimetry  2001 

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    Language:English

  7. 応用物理用語大事典

    ( Role: Joint author)

    オーム社  1998 

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    Language:Japanese

  8. "Simple, Quick and Precise Measurement of in-core Neutron Flux Distributions by Using Optical Fiber with Scintillator"

    C. Mori, Y. Mito, K. Kageyama, Y. Takenaka, K. Yanagida, A. Uritani, H. Miyahara Y. Wu, K. Kobayashi, C. Ichihara, S. Shiroya, M. Hayashi, H. Unesaki, I. Kimura, T. Iguchi and M. Nakazawa( Role: Sole author)

    Reactor dosimetry  1998 

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  9. Research for Application of Long Counter with a Position-Sensitive Proportional Counter to Neutron Dosimetry

    H. Toyokawa, A. Uritani, C. Mori, N. Takeda and K. Kudo( Role: Joint author)

    Reactor Dosimetry  1994 

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Presentations 706

  1. BNCT 場におけるPVA KI ゲル線量計の中性子評価に関する研究

    鈴木 応輔,吉橋 幸子,山崎 淳,瓜谷 章

    第55回日本原子力学会中部支部研究発表会  2023.12.14 

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    Event date: 2023.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  2. 高ガンマ線線量場で動作可能な10 B 中性子検出器の開発

    兼浦 知希,瓜谷 章,山崎 淳,吉橋 幸子,大村 幸一郎

    第55回日本原子力学会中部支部研究発表会  2023.12.15 

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    Event date: 2023.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  3. 先端核融合中性子源(A FNSFNS)のBNCT 応用におけるBSA 設計

    天野 翔太,西谷 健夫,吉橋 幸子,瓜谷 章,山崎 淳

    第55回日本原子力学会中部支部研究発表会  2023.12.15 

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    Event date: 2023.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  4. 犬悪性黒色腫細胞に対するBNCT の有効性評価

    土本 一貴,吉橋 幸子,山﨑 淳,岩崎 遼太,森 崇,瓜谷 章

    第55回日本原子力学会中部支部研究発表会  2023.12.14 

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    Event date: 2023.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  5. 伴侶動物を治療対象としたBNCT による臓器への影響評価に関する研究

    石川 裕也,吉橋 幸子,山崎 淳,瓜谷 章

    第55回日本原子力学会中部支部研究発表会  2023.12.14 

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    Event date: 2023.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  6. ホウ素中性子捕捉療法(BNCT)時における被ばく低減に関する基礎的検討

    新美秋桜, 吉橋幸子, 山崎 淳, 瓜谷 章

    日本放射線安全管理学会第 22 回学術大会  2023.11.12 

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    Event date: 2023.11

    Language:Japanese   Presentation type:Poster presentation  

    Venue:静岡県コンベンションアーツセンター  

  7. 犬悪性黒色腫細胞に対するBNCT効果の検証

    土本一貴、吉橋幸子、山﨑淳、瓜谷章

    日本保健物理学会第56回研究発表会  2023.11.10 

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    Event date: 2023.11

    Language:Japanese   Presentation type:Poster presentation  

    Venue:グランドニッコー東京台場ホテル  

  8. 動物BNCTの実現に向けた着脱式モジュールの設計と線量評価

    水口渉、吉橋幸子、山﨑淳、瓜谷章

    日本保健物理学会第56回研究発表会  2023.11.9 

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    Event date: 2023.11

    Language:Japanese   Presentation type:Poster presentation  

    Venue:グランドニッコー東京台場ホテル  

  9. BNCT適応対象拡大に向けたホウ素取り込み量と生存率の評価

    福富 太貴,吉橋 幸子,山﨑 淳,瓜谷 章

    日本原子力学会2023年秋の年会「学生連絡会ポスターセッション」  2023.9.6 

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    Event date: 2023.9

    Language:Japanese   Presentation type:Poster presentation  

  10. 名古屋大学BNCT 用中性子源Li 封入ターゲットの 性能向上に向けた特性評価に関する研究

    川口 直也,山﨑 淳,本田 祥梧, 吉橋 幸子, 瓜谷 章

    日本原子力学会2023年秋の年会「学生連絡会ポスターセッション」  2023.9.6 

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    Event date: 2023.9

    Language:Japanese   Presentation type:Poster presentation  

  11. 波長分解型光ファイバ放射線位置検出器を用いた福島第一原子力発電所における放射線分布測定

    寺阪 祐太、佐藤 優樹、瓜谷 章

    日本原子力学会2023年春の年会  2023.3.15 

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    Event date: 2023.3

    Language:Japanese   Presentation type:Oral presentation (general)  

  12. 血液がんのホウ素取り込み量とBNCT 線量の評価

    福富 太貴, 吉橋 幸子, 土田 一輝, 山崎 淳, 瓜谷 章

    第54回日本原子力学会中部支部研究発表会  2022.12.15 

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    Event date: 2022.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  13. 名古屋大学BNCT用加速器システム向上に向けたLIBS システムの適用に関する研究

    川口 直也, 立松 大武, 本田 祥梧, 山﨑 淳, 吉橋 幸子, 瓜谷 章

    第54回日本原子力学会中部支部研究発表会  2022.12.15 

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    Event date: 2022.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  14. 免疫蛍光染色を用いたホウ素中性子捕捉反応(BNCR)解明に向けた基礎的検討

    鈴木 一成, 瓜谷 章, 吉橋 幸子, 山崎 淳, 土田 一輝

    第54回日本原子力学会中部支部研究発表会  2022.12.15 

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    Event date: 2022.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  15. Simultaneous position detection of 90Sr/90Y and 137Cs using a liquid light guide Cerenkov counter

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    Event date: 2022.11

    Language:Japanese   Presentation type:Oral presentation (general)  

  16.  体外ホウ素中性子捕捉療法(Ex Vivo BNCT)による 自家造血幹細胞移植のための中性子照射システムの開発研究

    瓜谷章、古矢修一、市川康明、土田一輝、西谷健夫、吉橋幸子、 清井仁 、前田嘉信、笠井智成

    第18回日本中性子捕捉療法学会  2022.10.30 

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    Event date: 2022.10

    Language:Japanese   Presentation type:Poster presentation  

    Venue:つくば市  

  17. Liガラス粉末を用いた透明コンポジットシンチレータと光ファイバを組み合わせた中性子検出器の応答評価

    大島 裕也、渡辺 賢一、石川 諒尚、瓜谷 章

    第69回応用物理学会春季学術講演会  2122.3.22 

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    Event date: 2022.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  18. 精密昇温速度法を用いたBeOセラミックス板のグロー曲線解析

    佐々木 瑛麻、田中 誠也、菅原 理、杉岡 菜津美、永坂 光正、吉橋 幸子、瓜谷 章、渡辺 賢一、岡田 豪、眞正 浄光

    第69回応用物理学会春季学術講演会  2122.3.24 

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    Event date: 2022.3

    Language:Japanese   Presentation type:Poster presentation  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  19. 食塩のOSL特性に関する基礎研究

    劉 軼夫、永坂 光正、瓜谷 章、渡辺 賢一、吉橋 幸子、山崎 淳

    第69回応用物理学会春季学術講演会  2122.3.25 

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    Event date: 2022.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  20. BNCT用ダイナミトロン加速器におけるビームプロファイルモニターを用いたビームサイズの評価

    降簱 大河、吉橋 幸子、本田 祥梧、土田 一輝、山崎 淳、瓜谷 章

    日本原子力学会2022年春の年会  2022.3.17 

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    Event date: 2022.3

    Language:Japanese   Presentation type:Oral presentation (general)  

  21. BNCT用Li封入型ターゲットの元素分析のためのLIBSシステムの検討

    立松 大武、吉橋 幸子、山﨑 淳、本田 祥梧、川口 直也、小林 真、土田 一輝、瓜谷 章

    日本原子力学会2022年春の年会  2022.3.17 

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    Event date: 2022.3

    Language:Japanese   Presentation type:Oral presentation (general)  

  22. Evaluation of induced radioactivity generated in the LHD deuterium plasma experiments

    Sachiko Yoshihashi, Hayato Tamada, Makoto Kobayashi, Takeo Nishitani, Atsushi Yamazaki, Mitsutaka Isobe, Kunihiro Ogawa and Akira Uritani

    2021.12.18 

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    Event date: 2021.12

    Language:English   Presentation type:Oral presentation (general)  

  23. Thermal Neutron Measurement Capability of Single Crystal CVD Diamond Detector near the Reactor Core Region of UTR-KINK

    M.I. Kobayashi, S. Yoshihashi, H. Yamanishi, S. Sangaroon, K. Ogawa, M. Isobe, A. Uritani, M. Osakabe

    2021.12.18 

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    Event date: 2021.12

    Language:English   Presentation type:Oral presentation (general)  

  24. X 線後方散乱に基づく非破壊検査法の開発」

    楊 一唱、 瓜谷 章、 渡辺 賢一、 吉橋 幸子、 山﨑 淳

    第53回日本原子力学会中部支部研究発表会  2021.12.16 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  25. 臭化タリウム検出器の電極構造に関する基礎検討」

    椿山 邦見,吉橋 幸子,山崎 淳,瓜谷 章,人見 啓太朗,野上 光博,渡辺 賢一 3

    第53回日本原子力学会中部支部研究発表会  2021.12.17 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  26. NUANS 中性子場における人体ファントムを用いた組織別線量評価

    棚上 裕生 西谷 健夫,吉橋 幸子 土田 一輝 瓜谷 章,山崎 淳

    第53回日本原子力学会中部支部研究発表会  2021.12.17 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  27. BNCT 用ダイナミトロン加速器におけるビームプロファイルモニターを用いたビ ームサイズの評価」

    降簱 大河,吉橋 幸子,本田 祥梧,土田 一輝,山崎 淳,瓜谷 章

    第53回日本原子力学会中部支部研究発表会  2021.12.17 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  28. 食塩の OSL 特性に関する基礎研究」

    劉 軼夫、 永坂 光正、 山崎 淳、 吉橋 幸子、渡辺 賢一、瓜谷 章

    第53回日本原子力学会中部支部研究発表会  2021.12.17 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  29. BNCT 用 Li ターゲットの元素分析のための LIBS システムの検討

    立松 大武,吉橋 幸子,土田 一輝,釣田 幸雄,瓜谷 章,山崎 淳

    第53回日本原子力学会中部支部研究発表会  2021.12.17 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  30. 高強度中性子場におけるリアルタイム中性子計測のための光ファイバ型中性子検出器に関する研究

    渡辺 賢一、山崎 淳、吉橋 幸子、瓜谷 章、増田 明彦、松本 哲郎、原野 英樹、田中 浩基、櫻井 良憲、野上 光博、人見 啓太郎

    日本量子医科学会第1回学術大会  2021.12.10 

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    Event date: 2021.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  31. Novel one-sided readout type position-sensitive optical fiber radiation sensor based on the wavelength-resolving analysis International conference

    Y. Terasaka, K. Watanabe, A. Uritani

    2021.10.21  IEEE

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    Event date: 2021.10

    Language:English   Presentation type:Poster presentation  

    Venue:WEB  

  32. Neutron detector using a semi-transparent composite of powder Li glass scintillator International conference

    K. Watanabe, A. Ishikawa, A. Uritani

    2021.10.21  IEEE

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    Event date: 2021.10

    Language:English   Presentation type:Poster presentation  

    Venue:WEB  

  33. Liガラス粉末透明コンポジットシンチレータを用いた光ファイバ型中性子検出器の開発

    大島 裕也、渡辺 賢一、石川 諒尚、瓜谷 章

    第82回応用物理学会秋季学術講演会  2021.9.11 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  34. TRUST Liガラス中性子検出器の開発と特性評価

    石川 諒尚、久貝 大輝、渡辺 賢一、山崎 淳、吉橋 幸子、瓜谷 章

    第82回応用物理学会秋季学術講演会  2021.9.11 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  35. 光ファイバ型線量計の感度ばらつき低減に関する検討

    金子 和樹、渡辺 賢一、山崎 淳、吉橋 幸子、瓜谷 章

    第82回応用物理学会秋季学術講演会  2021.9.12 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  36. Liガラス粉末を用いた透明コンポジットシンチレータの開発

    渡辺 賢一、大島 裕也、石川 諒尚、瓜谷 章

    日本原子力学会2021年秋の大会  2021.9.9 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  37. 単結晶CVDダイヤモンド検出器の高速中性子計測のための波形弁別手法の開発

    小林 真、吉橋 幸子、小川 国大、磯部 光孝、神尾 修治、藤原 大、Siriyaporn Sangaroon、瓜谷 章、長壁 正樹

    日本原子力学会2021年秋の大会  2021.9.9 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  38. BNCT用Li封入型ターゲットの熱負荷低減のためのビーム走査方法についての検討

    冨田 誠之介、吉橋 幸子、本田 祥梧、土田 一輝、山崎 淳、渡辺 賢一、鬼柳 善明、瓜谷 章

    日本原子力学会2021年秋の大会  2021.9.8 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  39. LHD重水素実験において生成される誘導放射能の評価

    山田 隼人、吉橋 幸子、小林 真、西谷 健夫、渡辺 賢一、山崎 淳、磯部 光孝、小川 国大2,3、瓜谷 章

    日本原子力学会2021年秋の大会  2021.9.9 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  40. BNCT用ダイナミトロン加速器のビーム輸送モデル構築に関する研究

    降籏 大河、吉橋 幸子、本田 祥梧、土田 一輝、山崎 淳、瓜谷 章

    日本原子力学会2021年秋の大会  2021.9.8 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  41. ACE-J40HEを用いたBNCT用p-Li反応による中性子生成量の評価

    棚上 裕生、西谷 健夫、吉橋 幸子、山崎 敦、瓜谷 章

    日本原子力学会2021年秋の大会  2021.9.10 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB  

  42. 波長スペクトルアンフォールディングによる放射線源分布測定手法の開発と検証

    寺阪 祐太、渡辺 賢一、瓜谷 章

    日本原子力学会2021年春の年会  2021.3.18 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  43. Liガラスシンチレータを用いた光ファイバ型中性子検出器のガンマ線感度評価

    石川諒尚、渡辺賢一、山崎淳、吉橋幸子、瓜谷 章

    日本原子力学会2021年春の年会  2021.3.18 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  44. BNCT用 Li封入型ターゲット表面の熱解析

    冨田誠之介、吉橋幸子、本田祥吾、土田一輝、渡辺賢一、山崎淳、瓜谷章

    日本原子力学会2021年春の年会  2021.3.18 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  45. 光ファイバ型線量計作製の自動化およびその性能評価

    金子和樹、山崎淳、吉橋幸子、渡辺賢一、瓜谷 章

    日本原子力学会2021年春の年会  2021.3.18 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  46. 中性子ブラッグエッジ解析に対する機械学習の適用性検討

    西浦真介、渡辺賢一、吉橋幸子、山﨑淳、瓜谷 章

    第68回応用物理学会春季学術講演会  2121.3.17 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  47. Liガラスシンチレータを用いた光ファイバ型中性子検出器の熱中性子感度および出力線形性評価

    石川諒尚、渡辺賢一、山崎淳、吉橋幸子、瓜谷章

    第68回応用物理学会春季学術講演会  2121.3.16 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  48. BeO光刺激蛍光体を用いたBNCT場でのガンマ線線量評価

    渡辺賢一、中村悟、永坂光正、山﨑淳、吉橋幸子、瓜谷 章

    第68回応用物理学会春季学術講演会  2121.3.19 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  49. BeOセラミックの成分分離したTLグローピーク発光量と線量の関係

    永坂光正、渡辺賢一、山﨑淳、吉橋幸子、瓜谷章、中村 悟

    第68回応用物理学会春季学術講演会  2021.3.19 

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    Event date: 2021.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  50. 光ファイバ型線量計作製方法の自動化に関する検討

    金子和樹、瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    第52回日本原子力学会中部支部研究発表会  2020.12.18 

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    Event date: 2020.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  51. 臭化タリウム検出器の信号波形処理に関する基礎検討

    椿山 邦見、渡辺 賢一、吉橋 幸子、山﨑 淳、瓜谷 章、人見 啓太朗、野上 光博

    第52回日本原子力学会中部支部研究発表会  2020.12.18 

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    Event date: 2020.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  52. Development of radiation distribution sensing method based on wavelength spectrum unfolding using optical fiber sensor

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    Event date: 2020.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  53. Study and characterization of BeO OSL in BNCT field

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    Event date: 2020.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  54. Neutron Source for BNCT at Nagoya University - High Current Operation International conference

    Sachiko Yoshihashi, Kazuki Tuchida, Shogo Honda, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Yoshiaki Kiyanagi and Tsukasa Miyajima

    UCANS WEB 2020 

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    Event date: 2020.11 - 2020.12

    Language:English   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  55. Present status of Nagoya University Accelerator-driven Neutron Source(NUANS)

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    Event date: 2020.11

    Language:Japanese   Presentation type:Poster presentation  

    Country:Japan  

  56. Evaluation of Gamma-ray Sensitivity of an Optical Fiber-based Neutron Detector Using a Li-glass Scintillator International conference

    Akihisa Ishikawa, Kenichi Watanabe, Atsushi Yamazaki, Sachiko Yoshihashi, Akira Uritani

    IEEE NSS-MIC 2020  2020.11.4  IEEE

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    Event date: 2020.11

    Language:English  

    Venue:online  

  57. 小型加速器中性子源と高効率中性子回折装置を用いた結晶配向性の観察

    渡辺賢一、今井頌、山﨑淳、吉橋幸子、瓜谷章、田﨑誠司、佐藤節夫

    日本原子力学会2020年秋の大会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  58. 単結晶 CVDダイヤモンド検出器の波形弁別によるトリチウム増殖反応定量計測手法の開発

    小林真、吉橋幸子、小川国大、磯部光孝、神尾修治、藤原大、瓜谷章、長壁正樹

    日本原子力学会2020年秋の大会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  59. 後方散乱 X線検査用大型一次元検出器の虚像に関する検討

    松江俊樹、渡辺賢一、山崎淳、瓜谷章、吉橋幸子、豊川弘之、藤原健、萬代新一、伊佐英範

    日本原子力学会2020年秋の大会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  60. BeO OSLを用いた BNCT場でのガンマ線線量測定手法に関する詳細検討

    中村悟、山﨑淳、渡辺賢一、吉橋幸子、瓜谷章

    日本原子力学会2020年秋の大会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  61. 名古屋大学における BNCT用加速器型中性子源システム開発(2)Li封入型ターゲットの開発

    本田祥梧、吉橋幸子、土田一輝、鬼柳善明、釣田幸雄、渡辺賢一、山﨑淳、瓜谷章

    日本原子力学会2020年秋の大会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  62. 名古屋大学における BNCT用加速器型中性子源システム開発(1)システム開発の進捗状況

    吉橋幸子、土田一輝、瓜谷章、本田祥梧、渡辺賢一、山﨑淳、鬼柳善明、宮島司

    日本原子力学会2020年秋の大会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  63. 熱解析を用いたBNCT用Li封入型ターゲットの除熱性能評価

    冨田誠之介、吉橋幸子、本田祥梧、土田一輝、渡辺賢一、山崎淳、瓜谷章

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  64. 波⾧分解中性子イメージングに基づくTlBrの結晶性の評価

    渡辺賢一、松本伎朗、瓜谷章、野上光博、人見啓太朗、土川雄介、甲斐哲也、篠原武尚

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  65. 名古屋大学におけるLiターゲットを用いた加速器型中性子源の開発現状

    吉橋幸子、土田一輝、瓜谷章、渡辺賢一、山﨑淳、鬼柳善明

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Symposium, workshop panel (nominated)  

    Venue:WEB   Country:Japan  

  66. 光ファイバを用いた人体挿入可能な小型線量計の製作方法に関する検討

    金子和樹、平田悠歩、山崎淳、吉橋幸子、渡辺賢一、瓜谷章

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  67. CVDダイヤモンド検出器を用いたホウ素中性子捕捉反応の直接計測法の開発

    吉橋幸子、小林真、小川国大、磯部光孝、長壁正樹、渡辺賢一、瓜谷章

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  68. Liガラスシンチレータを用いた光ファイバ型中性子検出器のガンマ線に対する応答評価

    石川諒尚、渡辺賢一、山崎淳、吉橋幸子、瓜谷章

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  69. 中性子ブラッグエッジ解析におけるシングルフィッティング精度に関する研究

    西浦真介、渡辺賢一、吉橋幸子、山崎淳、瓜谷章

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  70. BeOセラミックの放射線誘起蛍光特性に関する研究

    永坂光正、渡辺賢一、山崎淳、吉橋幸子、瓜谷章、中村悟

    第81回応用物理学会秋季学術講演会 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:WEB   Country:Japan  

  71. BeOセラミックの放射線誘起の発光機構に関する調査

    永坂光正、瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    第32回放射線夏の学校  2020.8.20  応用物理学会放射線分科会

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    Event date: 2020.8

    Language:Japanese  

  72. Application of GM counting instrument to electrostatic pendulum

    MORI, Chizuo, URITANI, Akira, YAMAMOTO, Seiichi, KAMIYA, Hitoshi, SAGOH, Yutaka

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    Event date: 2020.7

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  73. 光ファイバー発光波長スペクトルのアンフォールディングに基づく一次元放射線分布測定法

    寺阪 祐太、渡辺 賢一、瓜谷 章、佐藤 優樹、鳥居 建男、若井田 育夫

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    福島第一原子力発電所(1F)の廃炉作業を円滑に進めるためには、線量率及び放射性物質の分布を詳細に把握する必要がある。これまでに登壇者らは光ファイバーを用いた新しい一次元放射線分布測定法として、ファイバー内での光の減衰量が波長依存であることを利用し、ファイバー片側から波長スペクトルを測定し発光位置分布を逆推定する「波長分解分析法」を提案し、基本的な線源位置分布測定が可能であることを確認した。本発表では波長分解分析法の位置決定精度やファイバーの耐放射線性に基づく適用範囲等について検証した結果を報告する。

  74. 核融合ブランケットにおけるトリチウム発生量実時間測定手法の開発

    小林 真、吉橋 幸子、小川 国大、磯部 光孝、神尾 修治、藤原 大、瓜谷 章、長壁 正樹

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    核融合炉ブランケットは、中性子の減速・遮蔽、トリチウムの増殖、熱の取り出しといった役割を有する。ダイヤモンド検出器はブランケットにおける高速中性子束やトリチウム発生量の実時間測定のための有用なモニタとして期待されるが、ガンマ線に感度を有するため、ガンマ線の寄与を適切に除す必要がある。
    本研究では単結晶CVDダイヤモンド検出器をリチウム材料と組み合わせ、中性子照射環境下で発生する高エネルギートリトンの直接測定を実施した。波形弁別と粒子輸送計算によりトリチウム発生量の定量手法について評価した。

  75. ダイヤモンド検出器によるホウ素中性子捕捉反応の直接定量手法の開発

    吉橋 幸子、小林 真、山本 優弥、小川 国大、磯部 光孝、長壁 正樹、渡辺 賢一、瓜谷 章

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    ホウ素中性子捕捉療法において、ホウ素と中性子の反応率(すなわち治療効果)を定量的に評価することが求められている。本研究グループでは、単結晶CVDダイヤモンド検出器とホウ素化合物とを組み合わせ、中性子照射下でホウ素中性子捕捉反応により発生する高エネルギー荷電粒子を直接測定する方法について評価を行っている。本発表では、中性子照射環境下でホウ素化合物から発生するアルファ線の直接測定およびアルファ線とガンマ線の波形弁別結果について報告する。

  76. 後方散乱X 線検査用大型一次元検出器の性能評価

    松江 俊樹、渡辺 賢一、山崎 淳、瓜谷 章、吉橋 幸子、豊川 弘之、藤原 健、萬代 新一、伊佐 英範

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    老朽化する大型インフラの長期保守管理をより効率的に行うために非破壊で内部情報を取得できる技術の開発が期待されている。X線を用いた非破壊検査の手法の中に後方散乱X線撮像法があり、この手法では被写体の片側にX線源と検出器を設置して検査を行うことができる。本研究においてはコリメータ等の重量物を稼働させることなく一次元プロファイルが取得可能なファンビームX線方式を採用している。この検査手法の課題として検査スピードの向上が挙げられている。そこでシンチレータをCWOからCsI:Tl結晶に変更、集光体系をCMOSカメラからフォトダイオードアレイに変更した検出器を製作し、性能を評価した。

  77. 炭素線治療の安全評価を目的とした光刺激蛍光体を用いた光ファイバー型小型線量計の開発

    平田 悠歩、金子 和樹、山﨑 淳、渡辺 賢一、吉橋 幸子、瓜谷 章、古場 裕介、松藤 成弘

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    炭素線治療はスキャニング照射法などの技術を用いて腫瘍のみを選択的に損傷させることが可能である。安全に治療を行うためには体内での線量評が求められている。そこで我々は光ファイバーの先端に光刺激蛍光体を配した小型線量計の開発を行っている。今回は、小型線量計の治療場での応用に向けて炭素線照射実験を行った。

  78. OSL線量計のBNCT場での運用に向けた検討

    中村 悟、平田 悠歩、山﨑 淳、渡辺 賢一、吉橋 幸子、瓜谷 章

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    BNCT照射場のような中性子が支配的で、実測困難なエネルギースペクトル場の人体に対するガンマ線量を正確に把握するために、我々は組成が人体に近く中性子感度が低いとされるBeOに注目し、OSL線量計として利用するための測定体系や測定方法を検討した。また、中性子とガンマ線が混在する場でガンマ線線量の実測を行った。

  79. 小型加速器中性子源用の高効率中性子回折装置の開発

    今井 頌、渡辺 賢一、山﨑 淳、吉橋 幸子、瓜谷 章、田﨑 誠司、佐藤 節夫

    日本原子力学会2020年春の年会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福島大学   Country:Japan  

    小型加速器中性子源での利用を想定した高効率な中性子回折計の開発を進めた。粉末中性子回折を想定し、柔軟性の高いTRUST Eu:LiCAFシンチレータを用いた円環状中性子検出器を多数配置し、大立体角を有する中性子回折計を製作し、京都大学加速器中性子源KUANSにて基礎試験を実施した。

  80. 波⾧分解中性子イメージングに基づくTlBr検出器製作過程の検討

    渡辺 賢一、松本 伎朗、瓜谷 章、野上 光博、人見 啓太朗

    第67回応用物理学会春季学術講演会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:上智大学四谷キャンパス   Country:Japan  

    TlBr検出器の開発の効率を図るためには、個々の製作プロセス間で、結晶の品質を評価可能な手法の開発が望まれている。本研究では、その試みの一つとして、中性子ブラッグディップ法を用いた評価手法を提案し、その特性について調べることを目的としている。

  81. 光刺激蛍光体と光ファイバーを用いた小型線量計のスキャニング法による炭素線治療場への応用

    平田 悠歩、金子 和樹、渡辺 賢一、山﨑 淳、吉橋 幸子、瓜谷 章、古場 裕介、松藤 成弘

    第67回応用物理学会春季学術講演会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:上智大学四谷キャンパス   Country:Japan  

    炭素線治療のスキャニング照射法は腫瘍にのみ集中的に線量付与することが可能である。安全に治療を行うためには体内での線量評が求められている。そこで我々は光ファイバーの先端に光刺激蛍光体を配した小型線量計の開発を行っている。今回は、小型線量計を用いてスキャニング法による炭素線治療場への応用を検討した。

  82. ダイヤモンド検出器を用いた荷電粒子計測手法の開発

    吉橋 幸子、小林 真、小川 国大、磯部 光孝、西谷 健夫、長壁 正樹、渡辺 賢一、瓜谷 章

    第67回応用物理学会春季学術講演会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:上智大学四谷キャンパス   Country:Japan  

    ダイヤモンド検出器の表面にリチウムやホウ素を含む化合物を付与することにより、(n,a)反応により発生するアルファ線や高エネルギー荷電粒子を直接測定することが可能である。本研究では、パルス波形弁別に基づくコードを確立し、リチウムやホウ素化合物を付したダイヤモンド検出器への中性子照射実験を行い、荷電粒子の定量評価を行う。

  83. Liガラスシンチレータを用いた光ファイバ型中性子検出器の出力線形性および放射線耐性

    石川 諒尚、山﨑 淳、渡辺 賢一、吉橋 幸子、瓜谷 章

    第67回応用物理学会春季学術講演会 

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    Event date: 2020.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:上智大学四谷キャンパス   Country:Japan  

    我々の研究グループでは、高強度中性子場において使用可能なリアルタイム中性子モニタとして、光ファイバ型中性子検出器の開発を行っている。本研究では、中性子検出媒体にLiガラスを用いて検出器を製作、その計数率特性を評価し、従来の約10倍の計数率においても出力線形性を維持できることを示した。さらに、放射線耐性の評価では、熱中性子フルエンス2×1012 n/cm2を超える中性子照射において、検出器の劣化は確認されなかった。

  84. Development of one-dimensional optical fiber type radiation distribution sensing method based on wavelength spectrum unfolding International conference

    Yuta Terasaka, Kenichi Watanabe, Akira Uritani, Atsushi Yamazaki, Yuki Sato, Tatsuo Torii and Ikuo Wakaida

    International Youth Nuclear Congress 2020 

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    Event date: 2020.3

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  85. 新方式波長分解分析型光ファイバー放射線分布センシング法の開発

    寺阪祐太、渡辺賢一、瓜谷章、山崎淳、佐藤優樹、鳥居建男、若井田育夫

    第2回日本放射線安全管理学会・日本保健物理学会合同大会 

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    Event date: 2019.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東北大学青葉山新キャンパス   Country:Japan  

  86. Development of a compact and highly efficient neutron diffractometer for compact accelerator neutron sources International conference

    Sho Imai, Kenichi Watanabe, Atsushi Yamazaki, Sachiko Yoshihashi, Akira Uritani, Seiji Tasaki, Setsuo Satoh

    3rd Asia-Oceania Conference on Neutron Scattering 

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    Event date: 2019.11

    Language:English   Presentation type:Poster presentation  

    Venue:Howard Beach Resort Kenting, Kaohsiung, Taiwan   Country:Taiwan, Province of China  

    Neutron diffraction is one of the structural analysis methods of materials. Unlike X-ray diffraction, neutron diffraction has the feature that neutrons can penetrate to the deep part of some materials, and analysis of light elements is possible. However, at present, facilities that can conduct neutron utilization research including neutron diffraction are limited to large facilities. In order to overcome such a situation, many compact accelerator neutron source (CANS) facilities are under development. It is important to effectively use neutrons in CANS because neutron intensity is low compared to large facilities. Therefore, it is desirable for neutron diffractometers to have large a solid angle. In general, neutron diffractometers that cover large solid angles are large and very expensive equipment. In this study, we aim to realize a compact and large solid angle neutron diffractometer. Our research group has been developing the Transparent rubber sheet type Eu:LiCaAlF6 (TRUST Eu:LiCAF scintillators), which are highly flexible neutron scintillators. It has become possible to make the circular neutron detectors by using the TRUST Eu:LiCAF scintillators and a wavelength-shifting fiber light readout system. A neutron diffractometer with a multiple ring structure consisting of many neutron detectors as shown in Fig. 1 was fabricated.
    Neutron diffraction experiments were carried out using one of such compact neutron sources in Kyoto University (KUANS). Although KUANS has low neutron flux, diffraction peak of silicon powder is clearly observed as shown in Fig. 2. This is because the diffractometer covers a large solid angle, and it has been demonstrated that a diffraction peak of a material having a low diffraction intensity such as silicon can be obtained at KUANS. In addition, iron powder diffraction pattern was measured. The minimum resolution of the 110 reflection is 3.0%. This resolution can be expected for engineering applications such as residual austenite measurement.

  87. Basic Study on New Configurations for Thallium Bromide Detectors International conference

    2019 IEEE Nuclear Science Symposium and Medical Imaging Conference in Manchester 

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    Event date: 2019.10 - 2019.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Manchester   Country:United Kingdom  

  88. Basic Study on Scintillation Properties of Mixed Powder Neutron Scintillators International conference

    2019 IEEE Nuclear Science Symposium and Medical Imaging Conference in Manchester 

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    Event date: 2019.10 - 2019.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Manchester   Country:United Kingdom  

  89. Study on sensitivity deterioration of luminescence dosimeters for energetic charged particles based on microdosimetry International conference

    2019 IEEE Nuclear Science Symposium and Medical Imaging Conference in Manchester 

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    Event date: 2019.10 - 2019.11

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Manchester   Country:United Kingdom  

  90. 新規中性子検出器開発に向けた混合粉末シンチレータに関する基礎研究

    石川 諒尚、山﨑 淳、渡辺 賢一、吉橋 幸子、瓜谷 章

    第80回応用物理学会秋季学術講演会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:北海道大学札幌キャンパス   Country:Japan  

    シンチレータ粉末とコンバータ粉末を混ぜ合わせる混合粉末シンチレータは、任意の組成を実現でき、シンチレータ選択の自由度を高めることが可能である。本研究では、コンバータとしてLiFを採用し、これと様々な蛍光体粉末を組み合わせて混合粉末シンチレータを製作し、既存の透明結晶シンチレータとの比較を通じて応答評価を行うことで、既存のシンチレータを凌駕する新規中性子検出媒体の開発に向けた基礎研究を行った。

  91. 光刺激蛍光体の粒子線に対する消光現象の比エネルギー計算を用いた考察

    平田 悠歩、渡辺 賢一、山﨑 淳、吉橋 幸子、瓜谷 章、古場 裕介、松藤 成弘、加藤 匠、河口 範明、柳田 健之

    第80回応用物理学会秋季学術講演会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:北海道大学札幌キャンパス   Country:Japan  

    粒子線の高線エネルギー付与(LET)領域では光刺激蛍光体は消光現象により感度が低下する。消光現象による感度低下は蛍光体内部のエネルギー付与密度に関係することが考えられる。今回は光刺激蛍光体の感度変化を比エネルギー計算により評価し実験により得られた結果と比較検討を行った。

  92. 臭化タリウム半導体検出器の大型化に向けたコプレナーグリッド型電極の検討

    松本 伎朗、渡辺 賢一、人見 啓太朗、野上 光博、吉橋 幸子、山﨑 淳、瓜谷 章

    第80回応用物理学会秋季学術講演会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学札幌キャンパス   Country:Japan  

    本研究は、TlBr検出器を大型化することで、高エネルギー分解能かつ高感度なTlBr検出器を開発することを目的としている。そのためには電極構造や信号読み出しの工夫が必要不可欠である。そこで、信号読み出し数が少なく、他の化合物半導体検出器でも実績のあるコプレナーグリッド型電極に着目し、TlBr検出器への適用を検討した。

  93. 後方散乱X線検査用検出器の高感度化に関する検討

    松江 俊樹、山崎 淳、渡辺 賢一、吉橋 幸子、瓜谷 章、豊川 弘之、藤原 健、萬代 新一、伊佐 英範

    第80回応用物理学会秋季学術講演会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学札幌キャンパス   Country:Japan  

    社会インフラ設備の長期保守管理をより効率的に行うことができる非破壊検査手法の一つに後方散乱X線検査がある。この手法では被写体の片側にX線源と検出器を設置して検査が可能である。本研究ではコリメータ等の重量物を稼働させずに1次元プロファイルを取得できるファンビームX線方式を採用し、ファンビームX線に直行する平行平板コリメータで散乱位置を限定している。先行研究で製作された検出器の要素検討を行いシンチレータと発光取得体系の変更した新たな検出器を製作した。

  94. 波長分解中性子イメージングによるTlBrの結晶性評価

    渡辺 賢一、松本 伎朗、人見 啓太朗、野上 光博、山﨑 淳、吉橋 幸子、瓜谷 章

    第80回応用物理学会秋季学術講演会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:北海道大学札幌キャンパス   Country:Japan  

    臭化タリウム(TlBr)は室温動作可能な化合物半導体検出器として期待されている。TlBr結晶の品質評価に、中性子ブラッグディップイメージングを適用した。ディップ波長の位置依存性が確認された。

  95. BNCT場でのガンマ線線量評価手法に関する検討

    中村 悟、瓜谷 章、渡辺 賢一、吉橋 幸子、山崎 淳、平田 悠歩

    第80回応用物理学会秋季学術講演会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:北海道大学札幌キャンパス   Country:Japan  

    BNCT照射場のような中性子が支配的で、実測困難なエネルギースペクトル場のガンマ線量を正確に把握するには、これら素子の中性子に対する感度評価や線量計応答のエネルギー依存性に関する詳細検討が必要である。そこで本研究では、中性子感度が低いと考えられているBeO熱刺激蛍光体(TLD)と、読出しが簡便で比較的安定性の高いC:Al2O3光刺激蛍光体(OSL)のBNCTへの適用性の検討を進めた。

  96. 波長分解型一次元光ファイバー放射線分布センシングに関する基礎検討 International conference

    寺阪 祐太、渡辺 賢一、瓜谷 章、花井 哲哉、佐藤 優樹、鳥居 建男、若井田 育夫

    日本原子力学会2019年秋の大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:富山大学五福キャンパス   Country:Japan  

    福島第一原子力発電所(1F)の廃炉過程における作業者の被ばく線量低減及び効率的な除染計画立案を行うためには、局所的に存在するホットスポットの分布を把握する必要がある。シンチレーション光ファイバーに飛行時間法を適用した広域一次元放射線分布測定システムが1F事故後に広く応用されてきたが、1F原子炉建屋内のような高線量率の環境では回路系のパイルアップやセンサーの偶発同時計数が問題となる。そこで、パイルアップ等の問題を回避できる積分型の測定手法として、光ファイバーの片側から波長スペクトルを読み出し、ファイバー内での光の減衰が波長依存であることを利用して放射線入射位置を特定する「波長分解法」の原理検証試験を実施した。

  97. ダイヤモンド検出器を用いたホウ素中性子捕捉反応の直接定量測定 International conference

    小林 真、吉橋 幸子、小川 国大、磯部 光孝、西谷 健夫、神尾 修二、藤原 大、坪内 知美、瓜谷 章、阪間 稔

    日本原子力学会2019年秋の大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:富山大学五福キャンパス   Country:Japan  

    ホウ素中性子捕捉療法に用いる中性子場の構築、人体内での中性子の減速過程の評価、治療効果のモニタリングのため、ホウ素中性子捕捉反応の実時間・定量測定が求められる。本研究では単結晶CVDダイヤモンド検出器をホウ素材料と組み合わせ、中性子照射下でホウ素中性子捕捉反応により発生する高エネルギーイオンを直接測定することで、ホウ素中性子捕捉反応発生率の定量評価手法を確立する。

  98. 核融合中性子を用いたBNCT治療効果の定量評価研究(1)研究概要・目的・体制

    小林真、坪内知美、吉橋幸子、小川国大、西谷健夫、磯部光孝、大坪瑶子、吉村信次、佐瀬卓也、横山須美、瓜谷章、阪間稔、長壁正樹

    第16回日本中性子捕捉療法学会学術大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学キャンパス宇治おうばくプラザ   Country:Japan  

    本研究では、生物・物理・医学・工学分野の研究者が連携することで、
    ホウ素中性子捕捉反応に伴う荷電粒子の発生を制御・計測し、DNAの
    二重鎖切断や細胞内DNA修復速度からBNCTの治療効果を定量する。

  99. 核融合中性子を用いたBNCT治療効果の定量評価研究(2)荷電粒子の定量測定法

    吉橋幸子、小林真、小川国大、磯部光孝、西谷健夫、長壁正樹、瓜谷章

    第16回日本中性子捕捉療法学会学術大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学キャンパス宇治おうばくプラザ   Country:Japan  

  100. 名古屋大学加速器BNCT用システムを用いた細胞評価について

    道上宏之、井川和代、古矢修一、市川康明、吉橋幸子、瓜谷章、渡辺賢一、鬼柳善明、土田一輝

    第16回日本中性子捕捉療法学会学術大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:京都大学キャンパス宇治おうばくプラザ   Country:Japan  

  101. 名古屋大学における加速器BNCT用システム開発(3) 封入型リチウムターゲットの開発

    吉橋幸子、本田祥梧、土田一輝、渡辺賢一、瓜谷章、釣田幸雄、鬼柳善明

    第16回日本中性子捕捉療法学会学術大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:京都大学キャンパス宇治おうばくプラザ   Country:Japan  

  102. 名古屋大学における加速器BNCT用システム開発(2)物理的特性評価

    渡辺賢一、石川諒尚、平田悠歩、中村悟、本田祥梧、吉橋幸子、瓜谷章、土田一輝、釣田幸雄、鬼柳善明

    第16回日本中性子捕捉療法学会学術大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:京都大学キャンパス宇治おうばくプラザ   Country:Japan  

  103. 名古屋大学における加速器BNCT用システム開発(1)全体概要

    瓜谷章、渡辺賢一、吉橋幸子、土田一輝、鬼柳善明、釣田幸雄、平田悠歩石川諒尚、本田祥吾、中村悟、市川豪、広田克也、清水裕彦、古矢修一、市川康明、松井秀樹、井川和代、道上宏之、植田愛

    第16回日本中性子捕捉療法学会学術大会 

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    Event date: 2019.9

    Language:Japanese   Presentation type:Poster presentation  

    Venue:京都大学キャンパス宇治おうばくプラザ   Country:Japan  

    名古屋大学では、2015年にダイナミトロン加速器を設置して以降、加速器の調整、中性子の発生、中性子場の特性評価を行ってきた。2016年度から2018年度にかけては、国立研究開発法人日本医療研究開発機構殿より岡山大学と共同で医療機器開発推進研究事業の委託を受け、1)中性子生成減速装置(BSA)の開発、 2)中性子照射場の特性評価、 3)BNCT線量評価、 4)加速器型BNCTガイドライン策定に向けた取組み、 5)非臨床試験(細胞実験) を行ってきた。本大会においては、中性子照射場の特性評価結果、中性子発生に用いるリチウムターゲットの開発状況、細胞実験結果について発表する。

  104. Thermal neutron flux evaluation by a single crystal CVD diamond detector in LHD deuterium experiment International conference

    Makoto Kobayashi, Kunihiro Ogawa, Mitsutaka Isobe, Takeo Nishitani, Shuji Kamio, Yutaka Fujiwara, Tomomi Tsubouchi, Sachiko Yoshihashi, Akira Uritani, Minoru Sakama, Masaki Osakabe and the LHD Experiment Group

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    Event date: 2019.5

    Language:English   Presentation type:Oral presentation (general)  

    Country:Portugal  

    The single crystal CVD diamond detector (SDD) was installed in the torus hall
    of the Large Helical Device (LHD) to measure neutrons with high time resolution and neutron
    energy resolution. The LiF foil with 95.62 % of 6Li isotope enrichment pasted on the detector was
    used as the thermal neutron convertor as the energetic ions of 2.0 MeV alpha and 2.7 MeV triton
    particles generated in LiF foil and deposited the energy into SDD.
    SDD were exposed to the neutron field in the torus hall of the LHD during the 2nd campaign
    of the deuterium experiment. The total pulse height in SDD was linearly propotional to the
    neutron yield in a plasma operation in LHD over 4 orders of magnitude. The energetic alpha and
    triton were separately measured by SDD with LiF with the thickness of 1.9 μm, although SDD
    with LiF with the thickness of 350 μm showed a broadened peak due to the large energy loss of
    energetic particles generated in the bulk of LiF. The modeling with MCNP and PHITS codes well
    interpreted the pulse height spectra for SDD with LiF with different thicknesses. The results above
    demonstrated the sufficient time resolution and energy discrimination of SDD used in this work.

  105. 名古屋大学加速器中性子源NUANSの現状 Invited

    瓜谷 章,土田 一輝,鬼柳 善明,渡辺 賢一, 吉橋 幸子,山崎 淳,釣田 幸雄,辻 義之, 恒吉 達矢,清水 裕彦,広田 克也,市川 豪, 今城 想平,土川 雄介,NUANSグループ

    J-PARCワークショップ 小型から大型中性子源の施設連携研究会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京大学 農学部 弥生講堂・一条ホール   Country:Japan  

  106. 中性子ブラッグエッジ解析コードRITSの不安定性に関する検討

    大前 良磨、渡辺 賢一、佐藤 博隆、鬼柳 善明、山﨑 淳、吉橋 幸子、瓜谷 章

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    中性子ブラッグエッジ解析コードRITSは非線形最小二乗フィッティングを行うものであるが、その収束値の不安定性を解消するための検討を行った結果を報告する。

  107. 名古屋大学における加速器BNCT用システム開発 (1) 全体概要

    瓜谷 章、土田 一輝、鬼柳 善明、渡辺 賢一、吉橋 幸子、山崎 淳、清水 裕彦、釣田 幸雄、広田 克也、今城 想平

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    名古屋大学で開発中の加速器BNCT用システムの整備進捗状況について発表する。ダイナミトロン型加速器を用いており、加速電圧は2.8MeV、最大電流は15mAである。本システムならびに各コンポーネントの概要と、特長、発生中性子の特性等について紹介する。

  108. 大型ヘリカル装置本体室内における放射化物の形成量の実験的評価

    山本 優弥、小林 真、田中 智代、吉橋 幸子、瓜谷 章、渡辺 賢一、山崎 淳、小川 国大、西谷 健夫、磯部 光孝

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    大型ヘリカル装置で実施された重水素プラズマ実験2ndキャンペーンにおいて放射化法を用いて構造材料の放射化物形成量を測定し、将来的な廃止措置に関わる放射化物の予測を行った。

  109. 名古屋大学における加速器BNCT用システム開発 (2) Li封入型ターゲットの開発

    本田 祥梧、吉橋 幸子、阿保 圭祐、土田 一輝、鬼柳 善明、釣田 幸雄、渡辺 賢一、山﨑 淳、瓜谷 章

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    本研究では、名古屋大学で開発中のBNCT用加速器型中性子源のLi封入型ターゲットの健全性について評価した。陽子エネルギー2.8MeV、電流1.5mAの陽子ビームを照射した結果、 Ti 箔は健全性を保ち、熱除去性能を達成したことを実験的に確認できた。

  110. 名古屋大学における加速器BNCT用システム開発 (3) 大電流加速器用ビームプロファイルモニターの開発

    吉橋 幸子、阿保 圭祐、本田 祥梧、土田 一輝、瓜谷 章、渡辺 賢一、山﨑 淳、鬼柳 善明

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    名古屋大学ではBNCT用加速器型中性子源を開発している。本装置では、中性子生成のために15mAの大電流静電加速器を用いる。ターゲットに適切にビームを照射するため、加速器からの陽子ビームの情報を得ることが重要である。本研究では、回転式プロファイルモニターを製作し、陽子ビームプロファイルおよびビーム位置の測定及び電流値が測定できることを実験的に確認した。

  111. 放射線治療中の患部周辺線量をモニターするための光ファイバーを用いた小型線量計の開発

    平田 悠歩、山﨑 淳、渡辺 賢一、吉橋 幸子、瓜谷 章、古場 裕介、松藤 成弘

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    粒子線治療などの放射線治療は精細な線量分布を形成することが可能である。安全に治療を行うために体内の実際に体内で線量測定を行うことが求められている。そこで我々は光ファイバーの先端に放射線誘起蛍光体を配した線量計の開発を行っている。今回は、線量計の実用化に向けて実際の治療場での応答評価試験など線量計の特性評価を行った。

  112. 臭化タリウム半導体検出器の大型化に関する検討

    松本 伎朗、渡辺 賢一、人見 啓太朗、長野 宣道、野上 光博、吉橋 幸子、山崎 淳、瓜谷 章

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    高エネルギー分解能を示す臭化タリウム半導体検出器の検出効率向上を目指し、検出器の大型化の際に問題となる事項に関する検討を行った。

  113. 高線量率用TOFシンチレーション光ファイバー放射線センサーの特性評価

    寺阪 祐太、佐藤 優樹、渡辺 賢一、瓜谷 章、鳥居 建男

    日本原子力学会2019年春の年会 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学水戸キャンパス   Country:Japan  

    シンチレーション光ファイバーセンサーに飛行時間法(Time-of-Flight法、TOF法)を適用した高線量率用TOF光ファイバー放射線センサーを開発した。ガンマ線照射場において照射試験を実施し、高線量率環境下での動作特性を評価した。

  114. 名古屋大学加速器中性子源の現状と フレキシブル検出器の開発 Invited

    瓜谷 章,土田 一輝,鬼柳 善明,渡辺 賢一,吉橋 幸子,NUANS Group

    平成31年電気学会全国大会 シンポジウム「原子力分野における中性子計測制御技術の展望」 

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    Event date: 2019.3

    Language:Japanese   Presentation type:Oral presentation (invited, special)  

    Venue:北海道科学大学   Country:Japan  

  115. 中性子ブラッグエッジ解析コードRITSにおけるシングルエッジフィッティングの改良

    大前 良磨、渡辺 賢一、瓜谷 章、山﨑 淳、吉橋 幸子、鬼柳 善明、佐藤 博隆

    応用物理学会春季学術講演会 

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    Event date: 2019.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:東京工業大学大岡山キャンパス   Country:Japan  

    中性子ブラッグエッジ解析コードRITSのシングルエッジ解析モードの不安定性を改善すべく、コードの改良を行った結果を報告する。

  116. 放射線治療中の患部周辺線量を評価するための放射線誘起蛍光体と光ファイバーを用いた小型線量計の開発

    平田 悠歩、渡辺 賢一、山﨑 淳、吉橋 幸子、瓜谷 章、古場 裕介、松藤 成弘、加藤 匠、河口 範明、柳田 健之

    応用物理学会春季学術講演会 

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    Event date: 2019.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:東京工業大学大岡山キャンパス   Country:Japan  

    粒子線治療などの放射線治療は精細な線量分布を形成することが可能である。安全に治療を行うために体内の実際に体内で線量測定を行うことが求められている。そこで我々は光ファイバーの先端に放射線誘起蛍光体を配した線量計の開発を行っている。今回は、線量計の実用化に向けて実際の治療場での応答評価試験など線量計の特性調査を行った。

  117. 光ファイバ型中性子検出器を用いたBNCT中性子場の計測

    石川 諒尚、山﨑 淳、渡辺 賢一、吉橋 幸子、瓜谷 章、釣田 幸雄、土田 一輝、鬼柳 善明

    応用物理学会春季学術講演会 

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    Event date: 2019.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:東京工業大学大岡山キャンパス   Country:Japan  

  118. TRUST Eu:LiCAFを用いた小型中性子回折装置の応答評価試験

    今井頌、渡辺 賢一、山﨑 淳、吉橋 幸子、瓜谷 章、田崎 誠司、佐藤 節夫

    応用物理学会春季学術講演会 

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    Event date: 2019.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:東京工業大学大岡山キャンパス   Country:Japan  

    中性子回折は物質の構造解析手法の一つであり、X線回折と相補的な関係にある。一般に大立体角中性子回折装置は大型になるが、本研究では柔軟な中性子シンチレータのTRUST Eu:LiCAFを用いることにより小型かつ大立体角の中性子回折装置を製作した。製作した中性子回折装置が中性子強度の高くない京都大学の小型加速器中性子源(KUANS)にて回折中性子を検知することができるか応答評価試験を行った。

  119. BNCT 用Li 封入型ターゲットの健全性評価

    本田祥梧,吉橋幸子,土田一輝,瓜谷章,渡辺賢一,山崎淳,鬼柳善明,辻義之, 恒吉達矢

    日本原子力学会中部支部 第50 回研究発表会 

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    Event date: 2018.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東桜会館   Country:Japan  

    名古屋大学は、Li ターゲットを用いたBNCT 用加速器中性子源の開発を行っている。Li ターゲットに
    入射する陽子ビームは、IBA 社製のダイナミトロン加速器で生成され、最大エネルギー2.8 MeV、電流15
    mA(42 kW)である。数MeV の低い陽子エネルギーでは、Li (p,n)Be 反応による中性子発生強度がBe(p,n)B
    反応と比較して髙いため、Li はBNCT 用のターゲットとして適している。しかしながら、金属Li の融点が180 度と低いことから、大電流の陽子を照射すると大量の熱が付与されLi が溶融してしまう問題がある。これらの問題を解決するため、冷却機能付きLi 封入型ターゲットを考案し、その開発を進めている。これまでに、乱流を促進する構造をもつ冷却チャンネルにより、冷却基板に照射される高熱流束(>15 MW/m2)を十分に除熱出来ることが電子ビームを用いた実験において確認した。本研究では、小型Li ターゲットを作製し、Li ターゲットの熱除去性能とTi 箔の健全性を陽子ビーム照射によって評価する。

  120. BNCT 場でのガンマ線量測定手法確立に関する検討

    中村悟,平田悠歩,山崎淳,渡辺賢一,吉橋幸子,瓜谷章

    日本原子力学会中部支部 第50 回研究発表会 

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    Event date: 2018.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東桜会館   Country:Japan  

    がんの新たな治療法の1 つとして現在、ホウ素中性子捕捉療法(BNCT)の研究が進められている。BNCT では患者に腫瘍細胞に集積する性質を持つホウ素化合物を体内に投与し、その後、体外から
    中性子照射を行うことで10B(n,α)7Li 反応を誘起して、放出されるα線と7Li 粒子によって腫瘍細胞を選択的に攻撃する治療法である。このBNCT で患者に与えられる線量は、10B(n,α)7Li 反応起因のホウ素線量、高速中性子起因の水素線量、14N(n,p)14C 反応起因の窒素線量とガンマ線量に分けて評価される。本研究では、この中のガンマ線量の評価法に関する検討を行っている。ガンマ線量の最も基本的な評価手法は電離箱を用いたものであるが、複雑な形状のファントム内での線量分布評価や、ホウ素薬剤の性能評価に用いられる細胞実験のように、電離箱を設置するのが困難な照射場におけるガンマ線量評価には、小型で電源不要な熱刺激蛍光体(TLD)や光刺激蛍光体(OSL)といった個人線量計素子の利用が望ましい。しかし、BNCT 照射場のような中性子が支配的な場でガンマ線量を正確に把握するには、これら素子の中性子に対する感度評価や線量計応答のエネルギー依存性に関する検討が必要である。そこで、中性子感度が低いと考えられているBeO 熱刺激蛍光体と、読出しが簡便で比較的安定性の高いC:Al2O3 光刺激蛍光体のBNCT への適用性の検討を進めた。

  121. Measurement of thermal and epithermal neutron flux distribution in the torus hall of LHD using activation method in 1st deuterium experiment campaign International conference

    2. T. Tanaka, M. Kobayashi, S. Yoshihashi, A. Uritani, K. Watanabe, A. Yamazaki, K. Ogawa, T. Nishitani, M. Isobe

    The 27th International Toki Conference on Plasma and Fusion Research & The 13th Asia Pacific Plasma Theory Conference 

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    Event date: 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Toki Japan   Country:Japan  

  122. Transparent mixed power neutron scintillator International conference

    K. Watanabe, M. Kataoka, N. Mitsuboshi, A. Yamazaki, S. Yoshihashi, A. Uritani, N. Kawaguchi, T. Yanagida, Y. Ikeda, K. Fukuda

    IEEE Nuclear Science Symposium 

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    Event date: 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:International Convention Centre Sydney, in Sydney,   Country:Japan  

    We are developing a new type of neutron scintillator. This type of scintillator consists of mixed powder of a neutron converter and a scintillator, like a famous LiF-Ag:ZnS neutron scintillator. The LiF-Ag:ZnS mixed powder is a very bright scintillator. However, the detection efficiency and effective thickness of this type of a neutron scintillator is limited because it is opaque due to quite high refractive index of the Ag:ZnS. Large gaps in the refractive index at interfaces of particles induce refractions with large angles. Therefore, scintillation photons must run for quite long path before escaping from a scintillator region. If mixed powder scintillator can be roughly transparent, we can freely change the scintillator composition, especially for lithium content and easily increase the scintillator thickness. Transparency of a mixed powder scintillator can be improved by choosing a converter and a scintillator with similar refractive indices and filling a refractive index buffer, such as liquid glass resin. We can choose a scintillator material with various properties, such as fast decay, high light yield etc. In this paper, we attempt to use LiF and Eu:CaF2 mixed powder to demonstrate a roughly transparent mixed powder neutron scintillator. The fabricated mixed powder scintillator was roughly transparent. We evaluated the scintillator responses for neutrons and gamma-rays. The scintillator showed a peak shape in a pulse height spectrum when irradiated with thermal neutrons.

  123. Basic analysis of OSL mechanism in an optical fiber type OSL dosimeter International conference

    Y. Hirata, K. Watanabe, A. Yamazaki, S. Yoshihashi, A. Uritani, T. Yanagida, K. Fukuda

    IEEE Nuclear Science Symposium 

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    Event date: 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:International Convention Centre Sydney, in Sydney,   Country:Japan  

    Radiotherapies are one of the main treatment modalities in cancer management. In order to accurately estimate the irradiation dose, it is better to insert a dosimeter into an affected region in a patient body. We, therefore, are developing a small size dosimeter consisting of an optical fiber and optically stimulated luminescence (OSL) elements. The OSL elements shows the quenching effect when high linear energy transfer (LET) particles are irradiated. In order to correct the quenching effect, using signal ratio from different OSL materials is considered to be effective. Since the effective correction could be achieved by using proper combination of OSL materials, various dosimeter materials are required to realize the suitable combination of OSL materials for the quenching effect correction. Investigation of the mechanism of the OSL process will help to look for new OSL elements. In this paper, we investigate the dependency on some parameters of exponential decay coefficients of the OSL signals in order to understand the OSL mechanism. We prepared the CaF2 OSL elements with different Ce dopant concentrations of 0.1, 0.5 and 1.0%. The OSL signals often have two decay components. The both decay coefficients linearly depend on the stimulation laser intensity. We compared the slopes of the decay coefficients in the OSL signals to the laser intensity for various Ce dopant concentrations. We confirmed that the slopes of the decay coefficients depend on the Ce concentration and decrease with the Ce concentration. These knowledge are expected to help to understand the OSL mechanism.

  124. Improvement of Linearity of Optical Fiber Type Neutron Detector Using a Small Piece of 6Li Based Scintillator International conference

    A. Ishikawa, A. Yamazaki, K. Watanabe, S. Yoshihashi, A. Uritani, T. Yanagida, K. Fukuda

    IEEE Nuclear Science Symposium 

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    Event date: 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:International Convention Centre Sydney, in Sydney,   Country:Japan  

    We are developing optical fiber type neutron detectors using a small piece of transparent Li-based scintillator as a real-time neutron monitor. This type of neutron detector consists of a small transparent scintillator, an optical fiber light guide and a photodetector, such as a photomultiplier tube. A wide dynamic range or wide linearity of signal output is one of the important specifications for neutron monitors. Especially, the counting rate often saturates in a high flux field. In high counting rate situation, this saturation behavior is caused by signal pulse pile-up. The pulse pile-up induces distortion of signal pulse shapes and counting losses. In our system, photomultiplier tube signals were integrated with a RC integrator and then processed with digital multi-channel analyzer (MCA) to extract pulse heights, detection timing and signal rise time. Signals through the RC integrator have an exponential decay component. In pulse pile-up events, signal pulse shapes were distorted by this decay component. The signal pulse heights were reduced in the pile-up events and depended on the counting rate. We implemented the pulse height correction function using information of detection time from a previous event and a previous pulse height in the signal processing procedures. This correction function successfully reduced distortion in pulse heights. In addition, we implemented the counting loss correction function. The corrected count rate shows no saturation behavior in a high count rate region over 100 kcps. The linearity of signal output was improved by the pulse height correction and the counting loss correction.

  125. Development of Thermal Neutron Moderator for Testing Boron Agents for Boron Neutron Capture therapy International conference

    Go Ichikawa, Tsuyoshi Hamano, Yuuho Hirata, Kazuyo Igawa, Akihisa Ishikawa, Yosiaki Kiyanagi, Ryo Ogawara, Mitsuru Suda, Kazuki Tsuchida, Akira Uritani, Kenichi Watanabe, and Sachiko Yoshihashi

    18th International Congress on Neutron Capture Therapy 

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    Event date: 2018.10 - 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Taipei, Taiwan   Country:Japan  

    We designed the moderator with a Monte-Carlo simulation code of PHITS based on a nuclear data JENDL-4.0.
    The source particles of the simulation are neutrons whose energy and momentum distributions are generated from a calculation code based on experimental data. The neutron yield from the target is 1.4 × 109 n/μC. The proton beam current was assumed to be 600μA. In order to maximize the produced thermal neutron flux, we planned to fill a collimator for fast neutron extraction hole with moderator material. We compared the thermal (<0.5 eV) neutron flux and the γray dose rate for the moderator of polyethylene, beryllium, graphite and polyethylene with a lead shield. The moderator of polyethylene with a lead shield can fit the condition for irradiation experiments of the thermal neutron flux of greater than several times 108 n/cm2/s and the γ ray dose rate of less than several Gy/h.
    Slots for irradiation samples are necessary for a realistic moderator design. We designed moderators with nine slots for cell sample tubes. The slots are located just below the lead layer to gain maximal thermal neutrons under the lead.
    We carried out the performance test of the moderator. The thermal neutron flux was measured with the gold foil activation method using foils of 2.5 × 2.5 mm with 10 μm thickness and cadmium shield with the thickness of 0.5 mm which can cover a gold foil. The radioactivity of gold foils was measured after the irradiation with a NaI scintillator and the thermal neutron flux was estimated by calculation using the radioactivity of gold foils and that covered by cadmium covers. The γray dose rates were measured by thermoluminescent dosimeters (TLDs).

  126. Rotary Type Beam profile monitor for Accelerator Driven BNCT System International conference

    Keisuke ABO, Sachiko YOSHIHASHI, Atsushi YAMAZAKI, Kenichi WATANABE, Akira URITANI

    18th International Congress on Neutron Capture Therapy 

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    Event date: 2018.10 - 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Taipei, Taiwan   Country:Japan  

  127. Compact Accelerator-Driven BNCT System Used Sealed Lithium Target International conference

    Kazuki TSUCHIDA, Yoshiaki KIYANAGI, Akira URITANI, Kenichi WATANABE, Sachiko YOSHIHASHI, Kazuy SATO, Daiki FURUZAWA, Yoshiyuki TSUJI, Tatuya TSUNEYOSHI, Hirohiko SHIMIZU, Katsuya HIROTA, Go ICHIKAWA, Akio SAGARA, Yukinori HAMAJI

    18th International Congress on Neutron Capture Therapy 

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    Event date: 2018.10 - 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Taipei, Taiwan   Country:Japan  

  128. Accelerator based BNCT system in Nagoya University -Development of a sealed lithium target International conference

    Sachiko YOSHIHASHI, Kazuki TSUCHIDA, Akira URITANI, Kenichi WATANABE, Yoshiaki KIYANAGI, Yukinori HAMAJI

    18th International Congress on Neutron Capture Therapy 

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    Event date: 2018.10 - 2018.11

    Language:English   Presentation type:Poster presentation  

    Venue:Taipei, Taiwan   Country:Japan  

  129. ブラッグエッジ解析を用いた日本刀研究

    及川 健一、鬼柳 善明、佐藤 博隆、大前 良磨、ファム ホァン アン、渡辺 賢一、松本 吉弘、篠原 武尚、甲斐 哲也、ハルヨ ステファヌス、大沼 正人、森戸 茂一、大庭 卓也、瓜谷 章、伊藤 正和

    第6回パルス中性子イメージング研究会 

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    Event date: 2018.10

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:エッサム神田ホール1号館 2F多目的ホール 201 号室   Country:Japan  

  130. 透明コンポジット中性子シンチレータの性能評価

    渡辺 賢一, 片岡 優斗, 山﨑 淳, 吉橋 幸子, 瓜谷 章, 河口 範明, 柳田 健之

    第79回応用物理学会秋季学術講演会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  131. 中性子ブラッグエッジ解析コードRITSにおけるエッジ フィッティング法に関する検討

    大前良磨, 渡辺賢一, 瓜谷章, 山﨑淳, 吉橋幸子, 鬼柳喜明

    第79回応用物理学会秋季学術講演会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  132. TRUST Eu:LiCAFを用いた小型中性子回折装置の製作

    今井 頌, 渡辺 賢一, 山崎 淳, 吉橋 幸子, 瓜谷 章

    第79回応用物理学会秋季学術講演会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  133. 6Liベース小片シンチレータを用いた光ファイバ型中性子 検出器の出力線形性

    石川 諒尚, 山﨑 淳, 渡辺 賢一, 吉橋 幸子, 瓜谷 章

    第79回応用物理学会秋季学術講演会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  134. 光ファイバー型小型線量計の放射線治療時の線量測定に向けた検討

    平田 悠歩, 渡辺 賢一, 山﨑 淳, 吉橋 幸子, 瓜谷 章, 古場 裕介, 松藤 成弘, 加藤 匠, 河口 範 明, 柳田 健之

    第79回応用物理学会秋季学術講演会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  135. Measurement of Neutron Spectrum using Activation Method in Deuterium Plasma Experiment at LHD International conference

    3. T. Tanaka, S. Yoshihashi, M. Kobayashi, A. Uritani, K. Watanabe, A. Yamazaki, K. Ogawa, T. Nishitani, M. Isobe

    30th Symposium on Fusion Technology 

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    Event date: 2018.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Sicily Italy   Country:Japan  

  136. 加速器BNCT用熱外中性子スペクトロメータの応答関数に関する検討

    須田 直樹、瓜谷 章、渡辺 賢一、吉橋 幸子、山崎 淳

    日本原子力学会2018年秋の大会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:岡山大学津島キャンパス   Country:Japan  

    加速器BNCTで患者に照射される熱外中性子(100~104 eV)のスペクトル測定に用いる検出器として、熱中性子シンチレータのEu:LiCAFを用い、中性子の減速材として従来のボナー球ではポリエチレンであったが本研究ではホウ素入りポリエチレンを用いた。ホウ素入りポリエチレンを減速材に用いることで熱外領域の中性子に高い感度を有する応答が得られた。

  137. 大電流陽子加速器におけるビームプロファイルモニタの設計・製作

    阿保圭祐、土田一輝、吉橋幸子、瓜谷章、渡辺 賢一

    日本原子力学会2018年秋の大会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:岡山大学津島キャンパス   Country:Japan  

    現在名古屋大学では、BNCTのためのDynamitron加速器が設置され調整中である。Liターゲットへ適切にビームを照射するため、加速器からの陽子ビームのプロファイルを取得することが重要である。Dynamitron加速器の最大電流は15 mAの大電流であり、その環境下で動作可能なBPMの検討を行った。

  138. Crystallographic structure study of a Japanese sword Noritsuna in Muromachi period using pulsed neutron imaging International conference

    Hirotaka Sato, Yoshiaki Kiyanagi, Kenichi Oikawa, Kazuma Oomae, Anh Hoang Pham, Kenichi Watanabe, Yoshihiro Matsumoto, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo, Masato Ohnuma, Shigekazu Morito, Takuya Ohba, Akira Uritani and Masakazu Ito

    11th World Conference on Neutron Radiography 

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    Event date: 2018.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Sydney   Country:Japan  

    Japanese swords are very attractive not only as a work of art but also a metallurgical point of view. There were five traditional styles (Gokaden) of Japanese sword-making in the Koto (old sword) age; A.D. 987-1596. Since Japanese vintage swords became valuable, it is indispensable to establish non-destructive analysis method to identify some peculiar characteristics, related to the forging methods. Neutron experiments are powerful tool to study metallic cultural heritages due to their high penetrating power and capability to give crystallographic information . Bragg-edge neutron transmission imaging gives real-space distributions of bulk information in a crystalline material. In addition, by analyzing position-dependent Bragg-edge transmission spectra measured at a pulsed neutron source, quantitative visualization of the crystallographic information of a sword can be achieved.
    In this work, we investigated crystallographic information of a Japanese sword made by Noritsuna in Bizen (one of Gokaden) in the fourth quarter of the 14th century. The experiments have been performed at the Energy-Resolved Neutron Imaging System, RADEN at J-PARC . The Noritsuna sword was measured at three regions with a counting-type 2D detector, nGEM. The measured position-dependent Bragg-edge transmission spectra were analyzed by the RITS code to obtain spatial distributions of the crystallite size, the texture variation, the d-spacing shift and its broadening. As a result, it was found that martensite phase exists near the blade, small crystallites were distributed at the tip region, and large crystallites were distributed at the stalk region. The crystallographic characteristics of Noritsuna, which are different from those of other swords, will be presented in detail.

  139. Comparison of crystallographic structures of Japanese swords in Muromach and modern periods by using pulsed neutron imaging International conference

    Y. Kiyanagi, K. Oikawa, H. Sato, K. Ohmae, P.H. Annh, K. Watanabe, Y. Matsumoto, T. Shinohara, T. Kai, S. Harjo, M. Ohnuma, S. Morito, T. Ohba, A. Uritani, M. Ito

    11th World Conference on Neutron Radiography 

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    Event date: 2018.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Sydney   Country:Japan  

  140. Comparative study of ancient and modern Japanese swords using neutron tomography International conference

    Yoshihiro Matsumoto, Kenichi Watanabe, Kazuma Ohmae, Akira Uritani, Yoshiaki Kiyanagi, Hirotaka Sato, Masato Ohnuma, Anh Hoang Pham, Shigekazu Morito, Takuya Ohba, Kenichi Oikawa, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo and Masakazu Ito

    11th World Conference on Neutron Radiography 

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    Event date: 2018.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Sydney   Country:Japan  

    Japanese swords have superior characteristics in strength and toughness, giving them important value not only as a historical work of art but also from a metallurgical point of view. It is known that Japanese swords differ in the forging technique depending on the era and place of manufacture. Modern Japanese swords are produced based on the forging techniques developed after the Edo period (17th - 19th century). On the other hand, with regard to ancient Japanese swords `Koto' forged from the Kamakura period to the Muromachi period (12th - 16th century), there are still many unknown points in the materials and forging techniques used due to lack of historical records. Therefore, evaluating the internal crystallographic structure of ancient Japanese swords and comparing them with modern Japanese swords are important footholds for reviving the lost forging techniques in the present age. From the above viewpoints, we have investigated the three-dimensional internal structure and crystallographic structure of ancient and modern Japanese swords non-destructively using neutron tomography and energy-resolved neutron imaging (Bragg-edge imaging). In this study, we report on the results of the neutron tomography measurement. All experiments were carried out at the pulsed neutron imaging instrument RADEN located at BL22 of J-PARC MLF [1].
    In the resulting neutron tomograms, it was observed that the neutron transmittance was different between steels near the surface and steels inside the blade in each of two ancient Japanese swords forged in the Muromachi period (named Morikage and Sukemasa) and a third modern Japanese sword (named Masamitsu) forged in the mid-20th century. This indicates that the martensitic phase was generated near the surface by quenching during forging. Furthermore, in the tomograms of the blade edge, it was observed that the neutron transmittance was distributed corresponding to the wavy pattern, referred to as `Hamon', particular to Japanese swords. Additionally, several line-like structures presumed to have been produced in the folding and forging processes were observed only in the modern Japanese sword. A detailed comparison of the results for the ancient and modern swords will be presented.
    Reference:
    [1] Shinohara, T.; Kai, T.; Oikawa, K.; Segawa, M.; Harada, M.; Nakatani, T.; Ooi, M.; Aizawa, K.; Sato, H.; Kamiyama, T.; Yokota, H., Sera, T., Mochiki, K., Kiyanagi, Y.; Final design of the Energy-Resolved Neutron Imaging System "RADEN" at J-PARC, J. Phys. Conf. Ser. 2016, 746, 012007.

  141. Crystallographic structure study of a modern Japanese sword Masamitsu using pulsed neutron imaging International conference

    Kazuma Oomae, Yoshiaki Kiyanagi, Hirotaka Sato, Kenichi Oikawa, Anh Hoang Pham, Kenichi Watanabe, Yoshihiro Matsumoto, Takenao Shinohara, Tetsuya Kai, Stefanus Harjo, Masato Ohnuma, Shigekazu Morito, Takuya Ohba, Akira Uritani and Masakazu Ito

    11th World Conference on Neutron Radiography 

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    Event date: 2018.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Sydney   Country:Japan  

  142. Crystallographic structure study of a Japanese sword Sukemasa in Muromachi period using pulsed neutron imaging International conference

    K. Oikawa, Y. Kiyanagi, H. Sato, K. Oomae, P.H. Ann, K. Watanabe, Y. Matsumoto, T. Shinohara, T. Kai, S. Harjo, M. Ohnuma, S. Morito, T. Ohba, A. Uritani, M. Ito J-PARC Center, Japan Atomic Energy Agency, Ibaraki, 9-9, Japan

    11th World Conference on Neutron Radiography 

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    Event date: 2018.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Sydney   Country:Japan  

  143. 名古屋大学における加速器BNCT用システム  -事業進捗状況と装置開発についてー

    吉橋 幸子、土田 一輝、鬼柳 善明、瓜谷 章、渡辺 賢一、山崎 淳

    第15回日本中性子捕捉療法学会学術大会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学学術交流会館   Country:Japan  

  144. In vitro evaluation system for accelerator based BNCT

    Jiatong Li,Kazuyo Igawa,Yasuaki Ichikawa,Syuichi Furuya,Toshiro Ono,Tadashi Hanafusa,Hideki Matui,Go Ichikawa,Kazuki Tsuchida,Yoshiaki Kiyanagi,Akihisa Ishikawa,Yuho Hirata,Sachiko Yoshihashi,Kenichi Watanabe,Akira Uritani,Ryo Ogawara,Mitsuru Suda,Tsuyoshi Hamano,Atunori Kamiya

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    BNCT has been active in the world stage as an innovative method of radiotherapy in recent years. Neutron therapy with 10B has an excellent effect on different kinds of cancer which have a poor prognosis in conventional surgery, radiotherapy and chemotherapy. The first BNCT for the adenocarcinoma (mucoepidermoid carcinoma) which have a recurrence after surgery and radiotherapy and refused to use conventional radiotherapy for further treatment was reported the quality of life and survival rate is improved. However, there are few facilities to evaluate the BNCR for new cancer candidate in vitro. Therefore, we report the in vitro evaluation system using accelerator based BNCT.

  145. BNCT用中性子源のLi封入型ターゲットの開発

    本田 祥梧、吉橋 幸子、土田 一輝、瓜谷 章、渡辺 賢一、山崎 淳、鬼柳 善明、 辻 義之、恒吉 達矢

    第15回日本中性子捕捉療法学会学術大会 

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    Event date: 2018.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学学術交流会館   Country:Japan  

  146. Measurement of Neutron Spectrum using Activation Method in Deuterium Plasma Experiment at LHD International conference

    1. T. Tanaka, A. Uritani, K. Watanabe, S. Yoshihashi, A. Yamazaki, M. Isobe, K. Ogawa, T. Nishitani, M. Kobayashi

    9th Japan-Korea Seminar on Advanced Diagnostics for Steady-State Fusion Plasmas 

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    Event date: 2018.8

    Language:English   Presentation type:Poster presentation  

    Venue:Toki Japan   Country:Japan  

  147. Sensitivity and Linearity of Optical Fiber Type Neutron Detector Using a Small Piece of 6Li-Based Scintillator International conference

    Ishikawa, Akihisa (1), Yamazaki, Atsushi , Watanabe, Kenichi, Yoshihashi, Sachiko (1), Uritani, Akira

    2018 Symposium on Radiation Measurements and Applications 

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    Event date: 2018.6

    Language:English   Presentation type:Oral presentation (general)  

    Venue:University of Michigan, USA   Country:Japan  

  148. Radiation damage evaluation of the optical ber type OSL small size dosimeter using for the radiotherapy dosimetry International conference

    Hirata, Yuho (1), Watanabe, Kenichi (1), Uritani, Akira (1), Yamazaki, Atsushi (1), Yoshihashi, Sachiko (1), Yanagida, Takayuki (2)

    2018 Symposium on Radiation Measurements and Applications 

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    Event date: 2018.6

    Language:English   Presentation type:Oral presentation (general)  

    Venue:University of Michigan, USA   Country:Japan  

  149. Basic study on a LiF-Eu:CaF2 mixed power neutron scintillator International conference

    Watanabe, Kenichi (1), Mitsuboshi, Natsumi (1), Ishikawa, Akihisa (1), Yamazaki, Atsushi (1), Yoshihashi, Sachiko (1), Uritani, Akira (1), Kawaguchi, Noriaki (2), Yanagida, Takayuki (2)

    2018 Symposium on Radiation Measurements and Applications 

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    Event date: 2018.6

    Language:English   Presentation type:Oral presentation (general)  

    Venue:University of Michigan, USA   Country:Japan  

  150. Present Status of Nagoya University Accelerator Driven Neutron Source, NUANS International conference

    Yoshiaki Kiyanagi, Kazuki Tsuchida, Daiki Furuzawa, Kazuya Sato, Atsushi Yamazaki, Sachiko Yoshihashi, Kenichi Watanabe, Akira Uritani, Yoshiyuki Tsuji, Tatsuya Tsuneyoshi

    7th International Meeting of Union for Compact Accelerator-driven Neutron Sources UCANS-VII 

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    Event date: 2018.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Bariloche, ARGENTINA   Country:Argentina  

    An accelerator driven neutron source is under construction at Nagoya University. There are two beam lines. The first beam line is used for the primary aim, namely, engineering feasibility study of a boron neutron capture therapy (BNCT) system. At the second beam line, physics and engineering applications are performed.
    An electrostatic proton accelerator with 2.8MeV and 15 mA was installed. The first beam line was constructed and a proton beam of about 2 mA was transported successfully. We use Be targets at the second beam line and also at the first beam line at beginning. They were already manufactured. A Li target is used to obtain full neutron intensity at the first beam line. It is a shield type compact target with emboss structure. It was indicated that the cooling power with the use of a mechanism to enhance turbulent flow was enough at the full power operation. A filling system of Li is under testing. A beam shaping assembly (BSA) with a nozzle for BNCT has been designed. The BSA will make a patient setting easier and a patient more comfortable during irradiation. Designed performance fulfilled the IAEA recommendation.
    We already got a license to produce the neutrons. However, to perform the neutron experiments, we are now constructing a shield room to set up the BSA. After completion of the room, we set up the first beam line completely and construct the second beam line.
    In the presentation, outline of NUANS, accelerator status, target development, BSA design are explained.

  151. Neutronic performance of a beam line for imaging at the electron linac facility in Kyoto University Research Reactor Institute International conference

    Yoshiaki Kiyanagi Yoshiyuki Takahashi, Akira Uritani, Kenichi Watanbe, Tadafumi Sano, Junichi Hori, and Ken Nakajima

    7th International Meeting of Union for Compact Accelerator-driven Neutron Sources UCANS-VII 

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    Event date: 2018.3

    Language:English   Presentation type:Poster presentation  

    Venue:Bariloche, ARGENTINA   Country:Japan  

    A neutron beam line at the Kyoto University electron linac, KURRI-LINAC, has been updated for a project called N-DeMAIN (Development of Non-Destructive Methods Adapted for Integrity test of Next generation nuclear fuels). As a non-destructive method, neutron resonance transmission analysis is adopted for identification and quantification of nuclides in the fuels. Furthermore, the method is also used to measure temperature distribution in the fuels.
    We redesigned a target-moderator-reflector system (TMRS) to suit for the imaging since it had been designed for nuclear data measurements. We first considered arrangement of a moderator to obtain highest neutron intensity. The neutron beam line exists at an angle of 135° with respect to the electron beam line. Therefore, we had two possibilities about a position of the moderator. One is to put a moderator near the target, and the other is at an angle perpendicular to the neutron beam line. In this case a distance between target and moderator become larger. We found that epithermal neutron intensity was much higher when the moderator was put near the target. However, it causes flight time difference of neutrons since neutron flight path length changes depending on emitted neutron positions on the moderator surface. This will make time resolution worse in the measurements of resonance peaks. Simulation results showed distorsion of neutron emission time distribution. However, it was found that the effect on a resonance peak was not so large. Simulations were also performed to check performance of a collimator system in a flight path and comfirmed the collimator system worked well. A measured neutron spectrum was almost the same as that of a simulation one. This indicates that the beam line was constructed as designed.
    Here, we explain neutronic design studies and performance of the TMRS and the collimator system, and introduce some results of test experiments.

  152. Neutronic performance of a beam line for imaging at the electron linac facility in Kyoto University Research Reactor Institute International conference

    Yoshiaki Kiyanagi, Akira Uritani, Kenichi Watanbe, Yoshiyuki Takahashi,Tadafumi Sano, Junichi Hori, Ken Nakajima

    7th International Meeting of Union for Compact Accelerator-driven Neutron Sources UCANS-VII 

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    Event date: 2018.3

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Bariloche, ARGENTINA   Country:Argentina  

    A neutron beam line at the Kyoto University electron linac, KURRI-LINAC, has been updated for a project called N-DeMAIN (Development of Non-Destructive Methods Adapted for Integrity test of Next generation nuclear fuels). As a non-destructive method, neutron resonance transmission analysis is adopted for identification and quantification of nuclides in the fuels.
    We redesigned a target-moderator-reflector system (TMRS) to suit for the imaging since it had been designed for nuclear data measurements. We first considered position of a moderator to obtain highest neutron intensity since the neutron beam line exists at an angle of 135° with respect to the electron beam line. We found that epithermal neutron intensity was much higher when the moderator was put near the target. However, it causes flight time difference of neutrons due to position dependent flight path of the moderator surrface. Simulation results showed distorsion of emission time distribution. However, the effect on a resonance peak was not so large. Simulations were performed to check performance of a collimator system. A measured neutron spectrum was almost the same as that of a simulation one. This indicates that the beam line was constructed as designed.
    Here, we explain neutronic design studies and performance of the TMRS and the collimator system, and introduce some results of test experiments.

  153. TRUST Eu:LiCAF による多重円環構造を採用した中性子回折計の製

    今井頌, 渡辺賢一, 山﨑淳, 吉橋幸子, 瓜谷章

    日本原子力学会中部支部 第 49 回研究発表会 

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    Event date: 2017.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東桜会館   Country:Japan  

    TRUST Eu:LiCAFシンチレータの柔軟性を活かした小型かつおおきな立体角を有する中性子回折計を設計し、モンテカルロシミュレーション計算により、その基礎特性を評価した。

  154. Eu:LiCaAlF6 およびLiF/Eu:CaF2 小片シンチレータを用いた 光ファイバ型中性子検出器の製作および応答評価

    石川諒尚,山﨑淳,渡辺賢一,吉橋幸子,瓜谷章

    日本原子力学会中部支部 第 49 回研究発表会 

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    Event date: 2017.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東桜会館   Country:Japan  

    加速器中性子源を用いたホウ素中性子捕捉療法(Boron Neutron Capture Therapy: BNCT) における患者の体表での中性子強度リアルタイムモニタリングへの適用を念頭に,光ファイバ先端に小片シンチレータを配した中性子検出器の開発を進めている.様々な強度の中性子場での使用を想定し,広いダイナミックレンジを有する光ファイバ型中性子検出器の実現に向けて検討を行っている.今回は,小片シンチレータに含まれる6Li 原子数を質量で管理し任意の感度の検出器を製作する方法の確立を目指すとともに製作した検出器の応答評価試験を行った.

  155. 混合粉末LiF-Eu:CaF2型中性子検出器に関する基礎検討

    三星夏海,渡辺賢一,吉橋幸子,山﨑淳,瓜谷章,柳田健之,河口範明

    日本原子力学会中部支部 第 49 回研究発表会 

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    Event date: 2017.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東桜会館   Country:Japan  

    本研究ではLiF とEu:CaF2 の混合粉末を用いた中性子シンチレータ検出器に関する検討を進めている。今回は、混合粉末を用い中性子シンチレータ検出器を製作し、その応答評価実験において中性子起因の信号が得られることを確認した。

  156. Construction of Nagoya University accelerator-driven Neutron Source, NUANS, 2nd Beam Line

    K. Hirota, Y. Tsuchikawa, S. Imajo, G. Ichikawa, I. Itoh, A. Uritani, M. Kitaguchi, Y. Kiyanagi, H. M. Shimizu, K. Tsuchida, A. Yamazaki, S. Yoshihashi, K. Watanabe, Y. Iwashita, Y. Yamagata

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    Event date: 2017.12

    Language:Japanese   Presentation type:Poster presentation  

    Country:Japan  

  157. Evaluation of a small neutron detector using a eutectic LiF/Eu:CaF2 scintillator and an optical fiber

    K. Watanabe, A. Ishikawa, A. Yamazaki, S. Yoshihashi, A. Uritani, N. Kawaguchi, T. Yanagida

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    Event date: 2017.12

    Language:Japanese   Presentation type:Poster presentation  

    Country:Japan  

  158. Development of Beam Shaping Assembly for BNCT system in Nagoya University International conference

    Kazuya SATO , Akira URITANI, Kenichi WATANABE, Sachiko YOSHIHASHI, Atsushi YAMAZAKI, Yoshiaki KIYANAGI and Kazuki TSUCHIDA

    9th Young Researchers' BNCT Meeting 

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    Event date: 2017.11

    Language:English   Presentation type:Poster presentation  

    Venue:Uji, Japan   Country:Japan  

  159. Evaluation Scheme of Boron 10 Compound for Accelerator-based Boron Neutron Capture Therapy International conference

    Kazuyo Igawa, Yasuaki Ichikawa, Shuichi Furuya, Hiroyuki Michiue, Toshiro Ono, Tadashi Hanafusa, Atsushi Fujimura,, Hideki Matsui, Go Ichikawa, Yoshiaki Kiyanagi, Sachiko Yoshihashi, Kenichi Watanabe, Daiki Furuzawa, Kazuya Sato, KazukiTuchida, Akira Uritani, Tsuyohi Hamano, Ryo Ogawara, Aurélie Morytko

    9th Young Researchers' BNCT Meeting 

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    Event date: 2017.11

    Language:English   Presentation type:Poster presentation  

    Venue:Uji, Japan   Country:Japan  

  160. Development of high heat removal technique for a sealed lithium target International conference

    10. Daiki FURUZAWA, Akira URITANI, Kenichi WATANABE, Sachiko YOSHIHASHI, Atsushi YAMAZAKI, Yoshiaki KIYANAGI, Kazuki TSUCHIDA, Yoshiyuki TSUJI, Tatsuya TSUNEYOSHI

    9th Young Researchers' BNCT Meeting 

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    Event date: 2017.11

    Language:English   Presentation type:Poster presentation  

    Venue:Uji, Japan   Country:Japan  

  161. Optical fiber type neutron detector using eutectic LiF/CaF2 scintillator International conference

    K. Watanabe, K. Fukuda, Y. Ikeda, A. Ishikawa, A. Yamazaki, S. Yoshihashi, A. Uritani, T. Yanagida

    2017 IEEE Nuclear Science Symposium and Medical Imaging Conference 

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    Event date: 2017.10

    Language:English   Presentation type:Poster presentation  

    Venue:Hyatt Regency, Atlanta, Georgia, U.S.A.   Country:United States  

    We are developing optical fiber type neutron detectors for relatively intense neutron fields, such as spallation neutron sources and irradiation fields of boron neutron capture therapy (BNCT). For the detectors used in these fields, the detection efficiency or sensitivity is not so important but no gamma-ray sensitivity and no influence to the measured field are strongly required. An optical fiber type neutron detector using a small piece of a bright neutron scintillator can suppress gamma-ray sensitivity preferentially to use difference in penetrating power between fast electrons and energetic charged particles generated in gamma-ray and neutron interactions, respectively. Of course, a small detector has little influence to the measured field. So far, we have applied a small piece of Eu:LiCaAlF6 scintillator for the optical fiber type neutron detector because of its high light yield and no hygroscopicity. In this paper, we replace Eu:LiCaAlF6 to eutectic LiF/CaF2:Eu scintillator. In this scintillator, LiF and CaF2 phases work as a converter from neutrons to energetic charged particles and a scintillator, respectively. It is expected to have higher neutron sensitivity due to its higher 6Li content than the LiCaAlF6 scintillator. We fabricated an optical fiber type neutron detector, in which a small piece of LiF/CaF2:Eu scintillator is mounted on a tip of an optical fiber. The fabricated detector also shows a neutron peak in the spectrum. Detectors showing a peak structure in the pulse height spectrum have advantages in stabilizing detector gain and assuring right operation.
    Keywords: neutron detector, eutectic LiF/CaF2:Eu, optical fiber

  162. Fabrication of hybrid small size dosimeter system using Eu:BaFBr and Ce:CaF2 for quenching effect correction International conference

    Y. Hirata, K. Watanabe, A. Uritani, A. Yamazaki, S. Yoshihashi, Y. Koba, N. Matsufuji, T. Yanagida, K. Fukuda

    2017 IEEE Nuclear Science Symposium and Medical Imaging Conference 

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    Event date: 2017.10

    Language:English   Presentation type:Poster presentation  

    Venue:Hyatt Regency, Atlanta, Georgia, U.S.A.   Country:United States  

    Particle radiotherapies can form fine and complex dose distribution and attack almost only a target organ or tumor. However, in fine irradiation, misalignment of an irradiation position might cause a significant accidental exposure to normal organs. In order to accurately estimate the irradiation dose, it is desired to insert a dosimeter into an affected region in a patient body. For this purpose, we are developing a small size dosimeter using optically stimulated luminescence (OSL) elements and an optical fiber, which has higher signal-to-noise ratio than scintillator based small size dosimeters. The OSL small size dosimeters showed quenching effects when irradiated by high linear energy transfer (LET) particles, such as carbon ions. The degree of quenching effect depends on OSL materials. The luminescence efficiency, that is also a correction factor for the quenching effect, can be determined from the luminescence ratio of the different OSL materials. In order to determine the luminescence ratio, we fabricated a hybrid small dosimeter probe, which is adhered with two types of OSL materials of Ce:CaF2 and Eu:BaFBr on a tip of a single optical fiber. We have already confirmed that this correction procedure using the hybrid probe can correct the quenching effect when the probe was irradiated with carbon ions with an energy of 290 MeV/u at Heavy Ion Medical Accelerator in Chiba (HIMAC). However, so far, we separately measured the signal intensities for the both OSL materials. This means that we measured two times at the same position for each OSL material. In this paper, we fabricated the OSL readout system for the hybrid small dosimeter probe in order to determine the luminescence ratio in a single measurement. We evaluate some characteristics on the hybrid probe measurement system.

  163. International trend of new radiation therapy using neutrons Invited International conference

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    Event date: 2017.10

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  164. Crystallographic characterization on different types of structure (Tsukurikomi) of Japanese swords using pulsed neutron imaging and diffraction methods International conference

    Kenichi Oikawa,Yoshiaki Kiyanagi, Kenichi Watanabe, Akira Uritani, Genki Hori, Yuho Hirata, Takenao Shinohara, Tetsuya Kai

    the 2nd International Conference on Neutron Imaging and Neutron Methods in Archaeology and Cultural Heritage (NINMACH) 2017 

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    Event date: 2017.10

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  165. Nondestructive evaluation of the microstructure of iron parts of traditional Japanese sword manufacturing process by pulsed neutron transmission spectroscopy International conference

    G. Hori, M. Tanaka, A. Yamazaki, K. Watanabe, Y. Kiyanagi and A. Uritani

    the 2nd International Conference on Neutron Imaging and Neutron Methods in Archaeology and Cultural Heritage (NINMACH) 2017 

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    Event date: 2017.10

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    In the case of iron cultural properties such as Japanese sword and matchlock gun, manufacturing techniques and material characteristics are not clear. To get detailed information about crystallographic characteristics of those iron artifacts is desired for elucidating them. In the analysis of precious iron cultural properties, nondestructive evaluation is preferable.
    Neutron has high penetrating power, and it is possible to get inside information nondestructively. Moreover, by using pulsed neutron transmission spectroscopy, we can obtain crystallographic information by analyzing the low-energy neutron transmission spectra including Bragg edges. The position and the shape of the Bragg edge give information such as strain, crystallite size, texture and density.
    It is considered to be useful to study such crystallographic parameter change of iron parts during making process to consider the effect of the making process to the crystallographic characteristics. Based on such information we will be able to guess the making process by the crystallographic information. We performed pulsed neutron transmission experiments for iron parts at different making stages and analyzed the transmission data by using the RITS code to obtain crystallographic information.

  166. 名古屋大学における加速器BNCT用システム -ノズル付きBSAの開発-

    佐藤和也 瓜谷章 渡辺賢一 吉橋幸子 山崎淳 鬼柳善明 土田一輝

    第14回日本中性子捕捉療法学会学術大会 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:郡山ビューホテルアネックス   Country:Japan  

    名古屋大学では静電加速器であるダイナミトロンとLiターゲットを使用したBNCT用中性子源の開発が進められている。本発表では、7Li(p,n)7Be反応により発生した高エネルギー中性子をBNCTに適した熱外領域まで減速し、ビーム状に整形するBeam Shaping Assembly(BSA)の改良設計の検討結果を紹介する。
    BSA内の中性子輸送の計算にはPHITSコード(ver.2.88)にJENDL-4.0を組み合わせて用 いた。Li薄膜に2.8 MeVの陽子を入射した際に発生する中性子エネルギー・角度分布 はLIYIELDコードを用いて計算した。従来までのBSA体系に延長コリメータを設置する ことで、患者への中性子ビーム照射が容易となる、下図に示す構成を得た。また、従 来までのBSA体系と延長コリメータを一体型にした新たな構造を検討し、熱外中性子束の大幅な向上が確認できた。以上の変更を施し、最終的に以下の結果を得た。これらの物理量はいずれもIAEA-TECDOCで取り上げられており、その推奨値をカッコ内に示す。

  167. 名古屋大学における加速器 BNCT 用システム -Li 封入型ターゲットの開発-

    吉橋幸子,古澤大貴,瓜谷章,渡邊賢一,山﨑淳,鬼柳善明,土田一輝, 辻義之,恒吉達也,浜地志憲,時谷正行

    第14回日本中性子捕捉療法学会学術大会 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:郡山ビューホテルアネックス   Country:Japan  

    名古屋大学は、Liターゲットを用いたBNCT用加速器中性子源の開発を行っている。Liターゲットに入射する陽子ビームは、IBA社製のダイナミトロン加速器で生成され、最大エネルギー2.8 MeV、電流15 mA(42 kW)が得られる。数MeVの低い陽子エネルギーでは、Li (p,n)Be反応による中性子発生強度がBe(p,n)B反応と比較して髙いため、Liがターゲットとして適している。しかしながら、放射性物質7Beを生成し、また融点が180度と低いことから、大電流の陽子を照射すると大量の熱が付与されLiが溶融してしまう問題がある。そこで、Liターゲットの問題を解決するため、冷却機能付きLi封入型ターゲットを考案し、その開発を進めている。本発表では、ターゲットの除熱試験とLi封入技術開発について報告する。

    ターゲットの除熱性能は、核融合科学研究所の超高熱負荷装置(ACT2)の30 keVの電子線を用いた加熱試験を行い、リブ構造を持った水冷チャンネルによって銅基板上への陽子ビームからの6.6 MW/m2高熱流束を除熱出来ることを確認した。その後、除熱性能をさらに向上させるため、流路の最適化を行い、さらなる性能の改善が達成できた。これにより、Liが溶融したとしても、液体Liと7Beとを安全にターゲット内に閉じ込めることが期待される。今後は、Li封入ターゲットと銅基板を接続したときの除熱性能を確認するため、各金属間の熱伝達を評価する予定である。

    Li封入型ターゲットは、エンボス構造を施したTa基板表面にTi箔を接合し、Ta基盤とTi箔の間にLiを封入する構造である。ターゲットの冷却は、Ta基板背面に接続した水冷チャンネルを有した銅基板により行う。Ti箔をTa基板に接合する技術開発は完了し、現在はLiを充填する方法の開発を進めると同時にTiとTaにおけるLiの濡れ性評価を行っている。

  168. 名古屋大学における加速器 BNCT 用システム -事業進捗状況と加速器について-

    土田一輝,鬼柳善明,瓜谷章,吉橋幸子,渡辺賢一,山﨑淳,古澤大貴,佐藤和也,清水裕彦,NUANSグループ

    第14回日本中性子捕捉療法学会学術大会 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:郡山ビューホテルアネックス   Country:Japan  

    名古屋大学では、静電加速器とLi封入ターゲットを組み合わせたBNCT用小型中性子源の開発を進めている。Liターゲットを用いた中性子源はBeターゲットに比べ必要とする陽子ビームのエネルギーが低くてすむので、中性子源を小型化でき、また装置の放射化がしにくい特徴を持つが、低融点金属であるLiや放射性7Beの保持方法とターゲット交換法が課題となっていた。この対策として、Liターゲット表面をTi箔で覆いLiや7Beをターゲット内に封じ込める「Li封入ターゲット」を考案、その開発を進めている(1)(2)。
    Liターゲットに入射する陽子ビームはIBA社製Dynamitron加速器を用いて生成する。これまでにIBA社工場にて陽子エネルギー2.8 MeV, 電流15 mAが5時間安定に得られることを確認している。名古屋大学工学部施設に搬入後、2.8 MeV, 電流11 mAの出力が得られることを確認、ターゲットまでのビームラインを追設、並行して中性子減速照射装置(BSA)の製作、ターゲット遠隔交換装置の設置を進めている。
    Li封入ターゲットの開発では、Ti箔をターゲット基板に接合する技術開発を完了し、現在、Ti箔とターゲット基板間にLi金属を充填する技術開発を進めている。ターゲット除熱技術に関しては、冷却水中の乱流を促進する構造をもつ冷却チャンネルを用いて、ターゲットに照射される高熱流束を十分に除熱できる性能(>15 MW/m2)を電子ビームを用いた予備実験で確認している(3)。
    Liターゲットから放出される高速中性子(最大エネルギー1MeV以下)を熱外領域まで減速するための中性子減速体については、モンテカルロ解析を用いて高速中性子混入率をIEAE TECDOG基準に準拠させながら熱外中性子束を最大とする「ノズル付きBSA構造」を開開発中である(4)。
    今後、「ダイナミトロン加速器」と、開発中の「Li封入ターゲット」「中性子減速体」を組み合わせて加速器BNCT用中性子源としての工学的性能を2017年度中に確認し、2018年からIn Vitro試験に供する予定である。

  169. Epi-thermal neutron spectrometer for BNCT

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  170. 名古屋大学加速器駆動小型中性子源 NUANS 2nd ビームラインの建設 International conference

    土川雄介, 阿保圭祐, 市川豪, 伊藤維久弥, 今城想平, 岩下芳久, 瓜谷章, 北口雅暁, 鬼柳善明, 佐藤和也, 清水裕彦, 竹下隼人, 土田一輝, 釣田幸雄, 広田克也, 古澤大貴, 三和田靖彦, 山形豊, 山崎淳, 吉橋幸子, 渡辺賢一

    日本物理学会 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:宇都宮大学   Country:Japan  

    名古屋大学では現在、加速器駆動型の小型中性子源 (NUANS) を建設している。NUANS は、ダイナミトロン静電加速器によって 2.8 MeV に加速した陽子ビームを、Li 及び Be 標的に照射することで核反応により中性子を生成する加速器駆動型の中性子源である。NUANS は、1) ホウ素中性子捕捉療法 (BNCT) の装置開発や、2) 中性子検出器等のデバイス開発及び中性子イメージングを目的とした2つの中性子ビームラインを持つ。本公演では、後者: 2nd ビームラインの性能や、現在の建設状況について報告する。

  171. コンクリート内部を可視化する後方散乱X線イメージング装置の開発

    豊川弘之、藤原健、萬代新一、伊佐英範、大橋和也、山崎淳、渡辺賢一、瓜谷章

    産総研 分析計測標準研究部門 第3回シンポジウム  

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:幕張メッセ国際会議場   Country:Japan  

    後方散乱X線イメージングを用いて道路や橋などのコンクリート構造物を非破壊検査する装置開発に関する研究を行った。電子加速器をベースとした高エネルギーX線発生装置および一次元の位置分解能を持つマルチスリットを備えたX線イメージング検出器を開発し、ファンビームX線を用いた後方散乱X線イメージングを試みた。本手法を実証するため試作装置を開発し、コンクリート構造物内部の可視化に成功した。

  172. コンクリート構造物の非破壊検査用後方散乱X線イメー ジング装置の開発

    大橋 和也,渡辺 賢一,山﨑 淳,瓜谷章,豊川 弘 之,藤原健,萬代新一,伊佐英範

    第78回応用物理学会秋季学術講演会 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福岡国際会議場・国際センター・福岡サンパレス   Country:Japan  

  173. 「講演奨励賞受賞記念講演」 光刺激蛍光体と光ファイバーを用いた小型線量計におけ る消光現象の補正方法の検討 Invited

    平田悠歩, 山﨑淳, 渡辺賢一, 吉橋幸子, 瓜谷章, 古場裕介, 松藤成弘, 歳籐利行, 柳田健之

    第78回応用物理学会秋季学術講演会 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (invited, special)  

    Venue:福岡国際会議場・国際センター・福岡サンパレス   Country:Japan  

  174. Present status of the BNCT neutron facility driven by an electrostatic proton accelerator at Nagoya University

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    Event date: 2017.8

    Language:Japanese   Presentation type:Poster presentation  

    Country:Japan  

  175. Development of Beam Shaping Assembly with extension collimator for Accelerator-based BNCT System in Nagoya University International conference

    Kazuya SATO, Akira URITANI, Kenichi WATANABE, Sachiko YOSHIHASHI, Atsushi YAMAZAKI, Yoshiaki KIYANAGI, Kazuki TSUCHIDA and Hirohiko SHIMIZU

    International Conference on Neutron Optics 2017  

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    Event date: 2017.7

    Language:English   Presentation type:Poster presentation  

    Venue:Nara, Japan   Country:Japan  

  176. Construction of Nagoya University Accelerator-driven Neutron Source (NUANS) 2nd beamline International conference

    Koichi Kino, Setsuo Sato, Kenichi Watanabe, Akira Uritani, Sachiko Yoshihashi, Atsushi Yamazaki, Yuichi Ikeda, Kentaro Fukuda

    International Conference on Neutron Optics 2017 

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    Event date: 2017.7

    Language:English   Presentation type:Poster presentation  

    Venue:Nara, Japan   Country:Japan  

    We have developed a neutron detection using Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST Eu:LiCAF) scintillator, in which small pieces of Eu:LiCAF scintillator is dispersed into the transparent rubber. The TRUST Eu:LiCAF is simple to make it large size because it can be fabricated with a rubber molding process. It is, therefore, suitable to combine with WaveLength Shifting Fiber (WLSF) which can collect scintillation photons from a large area detector. In this paper, we are developing a long detector with one-dimensional position sensitivity. One of the methods to obtain a one-dimensional detection position in the WLSF is to use the ratio between signal pulse heights obtained at the both ends. However, the light attenuation length in the optical fiber is generally too long to determine a detection position precisely. Applying appropriate optical processing in the fibers, we can make the signal difference large.
    We fabricated the one-dimensional position sensitive detector with 1000 mm long using 19 WLSFs of 1 mm diameter. Each fiber was divided into two pieces with a reflective face and has all different divided fractions. Since the divided fractions are distributed with equal interval of 50 mm through detector, the signal pulse heights at each end gradually change with the detection position. We experimentally confirmed the position sensitivity of the fabricated detector. The relative position resolution with respect to the fiber length was evaluated to be 16% as FWHM in neutron irradiation tests using Cf-252 source surrounded with polyethylene moderator.

  177. Development of Beam Shaping Assembly for Accelerator-based BNCT System in Nagoya University International conference

    Akira URITANI, Yosuke MENJO, Kazuya SATO, Kenichi WATANABE, Sachiko YOSHIHASHI, Atsushi YAMAZAKI, Yoshiaki KIYANAGI, Kazuki TSUCHIDA and Hirohiko SHIMIZU

    International Conference on Neutron Optics 2017  

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    Event date: 2017.7

    Language:English   Presentation type:Poster presentation  

    Venue:Nara, Japan   Country:Japan  

    An accelerator-driven compact neutron source for Boron Neutron Capture Therapy (BNCT) has been developed in Nagoya University since 2013. A Dynamitron accelerator and a Li target are used to generate neutrons. The 7Li(p, n)7Be reaction produce neutrons. Since the generated neutrons have considerably high energy, up to a few hundred keV, it is necessary to lower the neutron energy to an epi-thermal region that is suitable for BNCT. In this work, we have designed a Beam Shaping Assembly (BSA) that lowers the neutron energy and makes beam-like neutrons. The consists of a MgF2 moderator, a lead reflector, a radiation shield and a neutron collimator. The PHITS (Ver.2.660) code has been used to simulate the neutron transport in the BSA. This paper mainly describes two issues. One is optimization of the shape of the BSA, mainly the moderator, and the other is the dependence of the calculation results on the nuclear data, JENDL-4.0 and ENDF/B-VII.1.

  178. Development of One-Dimensional Position-Sensitive Neutron Detector Using TRUST Eu:LiCAF Scintillator International conference

    Hiroaki SHIMIZU, Koichi KINO, Setsuo SATO, Kenichi WATANABE, Akira URITANI, Sachiko YOSHIHASHI and Atsushi YAMAZAKI

    International Conference on Neutron Optics 2017  

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    Event date: 2017.7

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Nara, Japan   Country:Japan  

    We developed a one-dimensional position-sensitive neutron detector using a Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST Eu:LiCAF) scintillators and a newly proposed wavelength shifting fiber (WLSF) readout. The proposed position-sensitive WLSF readout consists of a number of the WLSFs optically divided to distinguish a scintillation position. We experimentally compared the position sensitivities of the optically divided WLSF type detector and the conventional one using light attenuation in the WLSFs. We concluded that the proposed detector had higher spatial resolution than that of the conventional one. We, additionally, fabricated the prototype detector of the optically divided WLSF type detector. We confirmed that the fabricated detector had the relative spatial resolution of approximately 20 %.

  179. Neutron Diagnostics in the Large Helical Devic International conference

    M. Isobe, K. Ogawa, T. Nishitani, H. Miyake, T. Kobuchi, N. Pu, H. Kawase, E. Takada, T. Tanaka, S.Y. Li, S. Yoshihashi, A. Uritani, Murakami, M. Osakabe and the LHD Experiment Group

    IEEE Symposium on Fusion Engineering  

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    Event date: 2017.6

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Shanghai Marriott Hotel City Centre Shanghai, China   Country:Japan  

    Deuterium operation of LHD and expected neutron emission rate
    Overview of neutron diagnostics prepared for LHD
    Neutron flux monitor -In situ calibration by using
    252Cf source -Initial measurement results
    Neutron activation system
    Vertical neutron camera
    Triton burnup study

  180. 熱外領域中性子エネルギースペクトルの測定法に関する一提案

    瓜谷章,渡辺賢一,山﨑淳,須田直樹,吉橋幸子

    平成29年度京都大学原子炉実験所専門研究会 「京都大学原子炉実験所のBNCT拠点としての効率化・高度化に関する研究会」 

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    Event date: 2017.5

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学原子炉実験所   Country:Japan  

  181. 名古屋大学加速器BNCT施設の開発状況

    瓜谷章,渡辺賢一,山﨑淳,佐藤和也,古澤大貴,辻義之,恒吉達也,鬼柳善明,土田一輝,清水裕彦,北口雅暁,広田克也,市川 豪,今城想平,吉橋幸子,若林俊彦,伊藤善之

    平成29年度京都大学原子炉実験所専門研究会 「京都大学原子炉実験所のBNCT拠点としての効率化・高度化に関する研究会」 

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    Event date: 2017.5

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学原子炉実験所   Country:Japan  

  182. Development of Nagoya University Accelerator-driven Compact Neutron Source (NUANS) International conference

    Katsuya Hirota, S. Imajo, G. Ichikawa, I. Itoh, M. Kitaguchi, H. M. Shimizu, Y. Tsuchikawa, Y. Kiyanagi, K. Tsuchida, A. Uritani, K. Watanabe, S. Yoshihashi, A. Yamazaki, Y. Iwashita, Y. Yamagata3 and JCANS Collaboration

    8th International Particle Accelerator Conference 

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    Event date: 2017.5

    Language:English   Presentation type:Poster presentation  

    Venue:Copenhagen, Denmark   Country:Denmark  

  183. コンクリート内部を可視化する後方散乱X線イメージング装置の開発 (2)検出器開発

    大橋和也、瓜谷章、渡辺賢一、山崎淳、豊川弘之、藤原健、萬代新一、伊佐英範

    日本原子力学会2017年春の年会 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学   Country:Japan  

  184. 名古屋大学における加速器BNCT用システム開発(2)Beam Shaping Assemblyの最適設計

    佐藤 和也、瓜谷 章、渡辺 賢一、吉橋 幸子、市川 豪、広田 克也、北口 雅暁、清水 裕彦、鬼柳 善明、土田 一輝

    日本原子力学会2017年春の年会 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学   Country:Japan  

  185. 名古屋大学における加速器BNCT用システム開発 (1)全体計画とその進捗について

    瓜谷 章、土田 一輝、鬼柳 善明、佐藤 和也、渡辺 賢一、吉橋 幸子、山﨑 淳、広田 克也、清水 裕彦、北口 雅暁

    日本原子力学会2017年春の年会 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学   Country:Japan  

  186. コンクリート内部を可視化する後方散乱X線イメージング装置の開発 (1)概要と全体システム

    豊川 弘之、藤原 健、萬代 新一、伊佐 英範、大橋 和也、山崎 淳、渡辺 賢一、瓜谷 章

    日本原子力学会2017年春の年会 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学   Country:Japan  

  187. 多重球殻構造を有する単一減速材球型中性子スペクトロメータのエネルギー応答に関する検討

    水越 友亮、渡辺 賢一、山﨑 淳、瓜谷 章、尾方 智洋、村松 貴史2

    日本原子力学会2017年春の年会 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学   Country:Japan  

  188. TRUST Eu:LiCAFを用いた一次元位置敏感型中性子検出器の開発

    志水 裕昭、木野 幸一、佐藤 節夫、渡辺 賢一、山崎 淳、吉橋 幸子、瓜谷 章

    日本原子力学会2017年春の年会 

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    Event date: 2017.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学   Country:Japan  

  189. BNCT用Beam Shaping Assemblyのγ線混入率に関する検討

    佐藤和也, 瓜谷章, 渡辺賢一, 吉橋幸子, 山崎淳, 市川豪, 広田克也, 北口雅暁, 清水裕彦, 鬼柳善明, 土田一輝

    日本原子力学会中部支部 第48回研究発表会 

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    Event date: 2016.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  190. 大型ヘリカル装置における放射化法を用いた中性子総発生量計測システムの感度校正

    田中智代, 李思遠, 普能, 瓜谷章, 渡辺賢一, 吉橋幸子, 山崎淳, 磯部光孝, 小川国大, 西谷健夫

    日本原子力学会中部支部 第48回研究発表会 

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    Event date: 2016.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  191. 3He代替位置敏感型中性子検出器の開発

    志水裕昭, 木野幸一, 佐藤節夫, 瓜谷章, 渡辺賢一, 吉橋幸子, 山崎淳

    日本原子力学会中部支部 第48回研究発表会 

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    Event date: 2016.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  192. Basic study of a Compton imaging using pixelated TlBr detectors

    Motohiro Matsumura, Kenichi Watanabe, Atsushi Yamazaki, Sachiko Yoshihashi, Akira Uritani, Hiroki Sunaba, Nobumichi Nagano and Keitaro Hitomi

    12th International Workshop on Ionizing Radiation Moitoring 

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    Event date: 2016.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Compton scattering cameras have exciting potentials for wide applications such as medical imaging, radioactive decontamination and so on. Thallium bromide (TlBr) is one of the promising candidates for detectors in the Compton scattering camera because they operate stably at room temperature and have good energy resolutions for gamma rays.
    The requirements for constructing Compton scattering cameras include good energy resolutions and good position resolutions for incident gamma rays. In case of pixelated detectors, the energy and position resolutions for near-anode events become worse because the pulse height decreases due to the weighting potential distortion. Charge-sharing events in adjacent pixels also contribute to deterioration of the energy and position resolutions. Therefore, development of pulse waveform analysis methods is necessary for using the pixelated TlBr detectors for the Compton scattering cameras.
    In this paper, we show that the pixelated TlBr detector was operated as the Compton scattering camera. Figure 1 shows an experimental geometry. The waveforms were obtained from the four pixels, the surrounding electrode and the cathode, with a digitizer. The experiment was run at room temperature. The digital signals from the detector were processed to estimate the positions of interactions and correcting the pulse heights of signals with the depth, off-line. Images reconstructed from two-pixel events on the diagonal line are illustrated in Figs. 2 and 3. The images of the source position were successfully reconstructed using the pixelated TlBr detectors at room temperature.

  193. A wide X-ray image sensor with extended field of view for backscattered X-ray imaging

    Kazuya Ohashi, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Hiroyuki Toyokawa, Takeshi Fujiwara, Hidenori Isa and Shinichi Mandai

    12th International Workshop on Ionizing Radiation Moitoring 

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    Event date: 2016.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Routine inspections and maintenances for aged infrastructures, such as bridges and tunnels, are required. One of the methods of non-destructive inspections is X-ray imaging. Transmission X-ray imaging inspection is, however, difficult for large structures because an X-ray source and a detector should be set across a huge object. Backscattered X-ray imaging technique can inspect a large structure from one side.
    We have developed a wide one-dimensional X-ray line sensor for the backscatter X-ray imaging inspection. This sensor consists of cadmium tungstate (CdWO4, CWO) scintillator sticks and stainless steel collimator plates. Each CWO stick is sandwiched between the collimator plates. Fan-beam X-rays is irradiated perpendicular to the collimator plates and to the object. The backscattered X-rays are detected with the CWO sticks. Since the field of view of each scintillator is restricted with the collimator plates, the one-dimensional backscattered X-ray profile is acquired. A two-dimensional image can be obtained by scanning the line sensor and the X-ray source.
    In order to extend the field of view of this line sensor, we increased the number of the CWO sticks. In order to increase the freedom of the configuration for scintillation light signal readout, we applied an optical fiber readout system. An end surface of each CWO stick is connected to an optical fiber and scintillation signals are detected at another end of the optical fiber.
    In order to check the performance of the fabricated system, we measured a concrete block having an iron rod inside.4

  194. Performance of Neutron Energy Spectrometer with Onion-like Single Bonner Sphere Using TRUST Eu:LiCAF Scintillator

    T. Mizukoshi, K. Watanabe, A. Uritani, A. Yamazaki, T. Iguchi, T. Ogata, T. Muramatsu, T. Matsumoto, A. Masuda

    12th International Workshop on Ionizing Radiation Moitoring 

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    Event date: 2016.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    In order to measure neutron energy spectra, the conventional Bonner Sphere Spectrometers (BSS) are widely used. Operators should place these spheres in several times to a measurement point where a radiation dose might be relatively high. In order to reduce this effort, a novel neutron energy spectrometer using an onion-like single Bonner sphere has been proposed by our group. This Bonner sphere has multiple sensitive spherical shell layers in a single sphere. In this spectrometer, a band-shaped thermal neutron detection medium, which consists of a Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST Eu:LiCAF) scintillator and a wavelength-shifting (WLS) fiber readout, was looped to each sphere at equal angular intervals. The amount of Eu:LiCAF neutron converter is reduced near polar region in order to uniform the directional sensitivity (Fig. 1). The TRUST Eu:LiCAF scintillator is flexible and shows a peak shape corresponding to thermal neutron absorption events in the pulse height spectrum. We fabricated the prototype detector with five sensitive layers using the TRUST LiCAF scintillators. The directionally variation of the detector sensitivity is less than 7% except the direction, in which there are PMTs, their supporting structures and a hole in the moderator sphere for drawing out the WLS fibers. The fabricated detector shows excellent directional uniformity of the neutron sensitivity.

  195. パルス中性子透過分光法を用いた日本刀の製造過程における組織変化の解析 International conference

    堀元紀、田中眞奈子、山﨑淳、渡辺賢一、鬼柳善明、瓜谷章

    日本中性子科学会第16回年会 

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    Event date: 2016.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    本研究グループは、これまでパルス中性子透過分光法を用いて非破壊で日本刀や火縄銃などの鉄文化財内部の結晶組織構造情報を解析し、具体的な製造方法や材料特性を解明することを目的に研究を行ってきた。前報では、パルス中性子透過分光法を用いて日本刀の製造過程の試料の測定を行い、鍛造や熱処理加工による結晶組織の変化を非破壊で確認した。本報では、同試料の棟から刃にかけて、2ピクセルごとに細かく解析を行い、場所による加工の影響を確認した。最終的には各製造過程における組織情報の2Dマッピング像を得ることを目的としている。
     結晶格子面間隔dに着目して解析したところ、焼入れを施す前の試料では刃から棟にかけての間隔は一定だが、施した後の試料では刀の棟では面間隔が小さくなり、刃では大きくなった。棟は焼入れの際に焼刃土が盛られる為、除冷されることで炭素量の小さいパーライトとフェライトに相変態し、刃は急冷され炭素量の多いマルテンサイトに変態したと思われる。棟と刃で異なる組織に変化した事で、面間隔に差が生じたと考えられる。その後の過程において焼き戻しを行った試料では、刃側の面間隔が少し小さくなった。再加熱によって炭素が抜け、組織が変化し、体積が縮小した為と考えられる。今後、まだ解析を行ってない製造過程試料の解析を進めていく予定である。

  196. 加速器駆動中性子源の現状と将来 Invited

    土田一輝,鬼柳善明,瓜谷章

    日本放射線安全管理学会 第15回学術大会 

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    Event date: 2016.11 - 2016.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:岡山大学 津島キャンパス   Country:Japan  

  197. Basic study of a Compton scattering camera using a pixelated TlBr detector International conference

    Motohiro Matsumura, Kenichi Watanabe, Atsushi Yamazaki, Sachiko Yoshihashi Akira Uritani, Hiroki Sunaba, Nobumichi Nagano and Keitaro Hitomi

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    Event date: 2016.10 - 2016.11

    Language:English   Presentation type:Poster presentation  

    Venue:Strasbourg, France   Country:France  

    Compton scattering cameras have exciting potentials for wide applications such as the medical imaging, radioactive decontamination and so on. Thallium bromide (TlBr) is one of the promising candidates for detectors in the Compton scattering camera because of operating stably at room temperature and the good energy resolutions for gamma rays.
    The requirements for constructing Compton scattering cameras include the good energy resolutions and the good position resolutions for incident gamma-rays. In case of pixelated detectors, the energy and position resolutions for near-anode events become worse because the pulse height decreases due to the weighting potential distortion. Charge-sharing events in adjacent pixels contribute also to deteriorate the energy and position resolutions. Therefore, development of pulse waveform analysis methods is necessary for using the pixelated TlBr detectors for the Compton scattering cameras.
    In this paper, we discuss the basic issues for using the pixelated TlBr detectors as the Compton scattering cameras. We have already demonstrated the depth-sensing capability in the pixelated detector by using anode/cathode signal ratio. However, the detector sharing a cathode for all pixels cannot reconstruct the depth-of-interaction from the anode/cathode ratio. We, therefore, adopt a new depth-sensing method, which derives the depth-of-interaction from electron drift time extracted with waveform processing. We confirmed that the depth-of-interaction estimated with the proposed procedure is well consistent with expectation from Compton scattering kinematics.

  198. Ce concentration dependence of quenching effects in Ce:CaF2 small size dosimeters International conference

    Yuho Hirata, Kenichi Watanabe, Akira Uritani, Atsushi Yamazaki, Yusuke KOBA, Naruhiro MATSUFUJI, Takayuki YANAGIDA, Kentaro FUKUDA

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    Event date: 2016.10 - 2016.11

    Language:English   Presentation type:Poster presentation  

    Venue:Strasbourg, France   Country:France  

    Heavy ion therapies can form fine and complex dose distributions and reduce undesired irradiation into normal organs. Misalignment of an irradiation position may cause significant accident. In order to accurately estimate the irradiation dose, dosimeters are required to be inserted into an affected region in a patient body. We, therefore, are developing a small size dosimeter consisting of an optical fiber and an optically stimulated luminescence (OSL) element. We evaluated the characteristics of OSL used small size dosimeters with a high energy carbon beam. OSL materials show quenching effects when irradiated by high linear energy transfer (LET) particles. We assumed the quenching effect was caused by local occupation of trap centers due to high density ionization. The quenching effect, therefore, depends on the density of trap centers. Ce:CaF2 is one of the most useful OSL elements. The OSL signal intensity is increased with Ce concentration. This means high Ce concentration make high density of trap centers. In this paper, we evaluate the quenching effect with different Ce concentration doped CaF2. We prepared different Ce concentration as 0.1, 0.5 and 5.0 % doped CaF2. Carbon ions were irradiated to the fabricated dosimeters at Heavy Ion Medical Accelerator in Chiba (HIMAC). The fabricated dosimeters were set behind the water equivalent acrylic phantom. The LET value of carbon ions were varied by changing the phantom thickness. The dosimeters showed different level quenching. Luminescence efficiencies increased with Ce concentration. We confirmed that the quenching effect depends on the density of trap centers.

  199. The design for BNCT facility based on radiation dose estimation International conference

    G. Ichikawa,Y. Kiyanagi, K. Tsuchida, A. Uritani, K. Watanabe, K. Hirota, H.M. Shimizu

    International Congress on Neutron Capture Therapy 17 

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    Event date: 2016.10

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  200. Design of a Beam Shaping Assembly for the Nagoya University BNCT Engineering Study System International conference

    Y. Menjo, Y. Kiyanagi, K. Tsuchida, A. Yamazaki, K. Watanabe and A. Uritani

    International Congress on Neutron Capture Therapy 17 

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    Event date: 2016.10

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    The proton energy is low and Li produces higher neutron intensity than Be at this energy. We decided to use a sealed Li target. The beam shaping assembly (BSA) will be different from the one designed for higher energy protons. In order to manufacturing a high efficiency BSA, we performed simulation calculations to design a sealed Li target BNCT system that fullfiled the conditions indicated in IAEA-TECDOC-1223.

  201. CompactAccelerator-DrivenBNCT SystemUsed Sealed LithiumTarget International conference

    K. Tsuchida, Y. Kiyanagi, A. Uritani, K. Watanabe, S. Yoshihashi, Y. Menjo, D. Furuzawa, Y. Tsuji, T. Tsuneyoshi, H. Shimizu, K. Hirota, G. Ichikawa, A. Sagara and Y. Hamaji

    17th International Congress on Neutron Capture Therapy 

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    Event date: 2016.10

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    A compact sealed lithium target is underdevelopingfor BNCT application in combination with a Dynamitron(2.8MeV,15mA). Low energy protons incident on lithium target are one of the most suitable reaction for accelerator-based BNCT [1, 2], because a sufficient flux and good quality of epi thermal neutron beam can be obtained by using a compact beam shaping assembly (BSA) and also radiationexposer of medical staffs can be reduced by lowering the activationof accelerator facility. However, metallic lithium has several difficulties in chemical properties (low melting point, high chemical activityand 7Be production) as a target material. For resolving those isssues, we are developing a compactand sealedLi target. A thin lithium layer (0.14mm) is set on the embossed structure of a tantalum plate and coveredby a thin titanium alloy foil to confine liquid lithium and radio isotopes (Be-7, T) in the target. The low-energy and high current proton beam is passing through a titanium foil and irradiated to the lithium layer. Strong turbulent flow is arose with ribs in cooling water channels of the target and had been confirmed to be able to remove high beam flux of more than 10MW/m2. It can reduce the irradiation area of the proton beam (42kW) down to the60mm squareon theLi target Neutrons withtheenergies ofless than1MeV are produced duetothe 7Li(p,n)7Bereaction by the irradiation of the 2.8MeV proton beams and could be moderated using a compact beam shaping assembly (1m in dia.) to meet all the conditions indicated in the IAEATECDOC-1223.
    We are constructing a compact accelerator-driven neutron source to confirm the practical reliability of thesealed lithiumtargetfortheBNCTapplication in theNagoya University.

  202. 名古屋大学NUANSの中性子発生ターゲットの研究開発

    瓜谷 章

    日本原子力学会2016年秋の大会 

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    Event date: 2016.9

    Language:Japanese   Presentation type:Oral presentation (invited, special)  

    Venue:久留米シティプラザ   Country:Japan  

  203. TRUST Eu:LiCAFを用いた多重球殻構造を有する一球型中性子スペクトロメータの評価

    水越友亮、渡辺賢一、瓜谷章、山崎淳、井口哲夫、尾方智洋、村松貴史、松本哲郎、増田明彦

    日本原子力学会2016年秋の大会 

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    Event date: 2016.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:久留米シティプラザ   Country:Japan  

  204. 光刺激蛍光体を用いた光ファイバ型小型線量計のヘリウム線に対する基礎的な応答の評価

    平田悠歩、瓜谷章、渡辺賢一、吉橋幸子、山﨑淳、古場裕介、松藤成弘、歳藤利行、柳田健之、福田健太郎

    日本原子力学会2016年秋の大会 

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    Event date: 2016.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:久留米シティプラザ   Country:Japan  

  205. Nondestructive study on metallurgical characteristics of traditional Japanese sword throughout the manufacturing process by pulsed neutron imaging International conference

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    Event date: 2016.9

    Language:English   Presentation type:Oral presentation (general)  

    Country:United States  

  206. A Design Study of a Neutron Source for Pulsed Neutron Imaging at Kyoto University Research Reactor Institute Linac International conference

    Y. Kiyanagi, A. Haradda, A. Uritani

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    Event date: 2016.9

    Language:English   Presentation type:Oral presentation (general)  

    Venue:北京   Country:China  

  207. Development of the Electrostatic Accelerator driven BNCT neutron source at Nagoya University

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    Event date: 2016.8

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    A neutron source based on an electrostatic accelerator, Dynamitron (2.8MeV, 15mA), is under construction at Nagoya University. The neutron source is planned to be used for boron neutron capture therapy and for science and engineering applications. Due to the low proton energy a Li target is used to obtain much higher neutron intensity than a Be target. The accelerator was installed in 20015. The first beam was delivered at 2.8MeV and 11mA in January 2016. Commissioning is underway for stable operation. A design study on a beam shaping assembly (BSA) has been performed under the condition of the IAEA-TECDOC-1223. A BSA that can produce epi-thermal neutron intensity over 109 n/cm2/sec was designed fulfilling the condition. Heat removal is one of serious issues of the Li target. Therefore, we performed preliminary experiment using an electron beam heating method. The result indicated that the cooling system developed will be able to remove the heat expected at full power accelerator operation.

  208. 名古屋大学における加速器BNCT 用システムの開発―(1)事業概要と加速器について ―

    土田一輝、鬼柳善明、瓜谷章、渡辺賢一、吉橋幸子、山崎淳、清水裕彦、北口雅暁、広田克也、市川豪、NUANS グループ

    第13回日本中性子捕捉療法学会学術大会 

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    Event date: 2016.8

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京大学伊藤国際学術研究センター 伊藤謝恩ホール   Country:Japan  

  209. 名古屋大学における加速器BNCT 用システムの開発―(3) Li 封入型ターゲットの除熱方法の検討 ―

    古澤大貴、瓜谷章、山崎淳、鬼柳善明、土田一輝、辻義之、恒吉達矢、浜地志憲、時谷政行、田村仁、相良明男

    第13回日本中性子捕捉療法学会学術大会 

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    Event date: 2016.8

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京大学伊藤国際学術研究センター 伊藤謝恩ホール   Country:Japan  

  210. 名古屋大学における加速器BNCT 用システムの開発―(2)Beam Shaping Assembly の設計検討 ―

    瓜谷章、校條洋輔、土田一輝、鬼柳善明、清水裕彦、広田克也、市川豪、渡辺賢一、山﨑淳、吉橋幸子、NUANSグループ

    第13回日本中性子捕捉療法学会学術大会 

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    Event date: 2016.8

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京大学伊藤国際学術研究センター 伊藤謝恩ホール   Country:Japan  

  211. Development of Accelerator-based BNCT System in Nagoya University 3

    Akira Uritani, Yosuke Menjo, Kenichi Watanabe, Atsushi Yamazaki, Katsuya Hirota, Masaaki Kitaguchi, Hirohiko Shimizu,Go Ichikawa, Yoshiaki Kiyanagi and Kazuki Tsuchida

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    Event date: 2016.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  212. Basic response evaluation of optical fiber type small size dosimeter using optically stimulated luminescence for 225 MeV/u proton ions

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    Event date: 2016.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  213. Neutron Energy Spectrometer with Onion-like Single Bonner Sphere Using TRSUT Eu:LiCAF Scintillator for High Flux

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    Event date: 2016.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  214. Development of high-energy x-ray backscatter imaging system for nondestructive inspection of reinforced concrete

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    Event date: 2016.2

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  215. Pulsed neutron Bragg-edge transmission analysis of steel materials with different carbon content for applied research of iron cultural heritages International conference

    M. Isono, M. Tanaka, Y. Shiota, K. Watanabe, Y. Kiyanagi and A. Uritani

    15th Japan-Korea meeting on Neutron Science  

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    Event date: 2016.1

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Detailed information such as raw materials, manufacturing techniques, material properties, producing areas and so on is still unclear concerning iron cultural heritage like Japanese sword and matchlock gun. Optical microscope, X-ray diffraction, EBSD and SEM have been used to get surface metallurgical information and to clarify their material characteristics. Most of the time, destruction of the sample is required for those analysis. However, non-destructive analysis is desired for the study of iron cultural heritage to keep their original shape and value.
    Neutron has a high penetrating power for materials. So, by using neutron, it is possible to measure material characteristics of the inside of metal materials nondestructively. Pulsed neutron transmission spectroscopy is a new method and it's getting clear that an image indicating strain, crystallite size, crystalline orientation, crystal phase fraction, density of the material can be obtained by using the TOF energy analysis at a pulsed neutron source.
    Four different carbon content steels of S25C (about 0.25mass%C), S50C (about 0.50mass%C), SK3 (about 1.0mass%C), and FC350 (about 3.0mass%C) were measured nondestructively by using a pulsed neutron transmission spectroscopy. The experiment was carried out at J-PARC/MLF BL10. The purpose of this work is to obtain a crystal structural information from the analysis of the Bragg edges (Fig. 1). The final goal of our study is to apply the results for the nondestructive research of iron cultural heritage such as Japanese sword and matchlock gun which were made of different carbon content steels .
    Figure 1 shows the neutron transmission spectrum of S25C, S50C, SK3, and FC350. Each sample shows a distinctive shape of the Bragg edge, which provides information on texture. We obtained the lattice spacing d by analyzing the position of (110), (200), and (211) edges. As shown in Fig.2, steel samples less than 1.0mass%C have no significant difference on lattice constant. On the other hand, lattice constant of steel about 3.0mass%C decreases. This may be due to the formation of the graphite and/or the impurities in steel. It is concluded that lattice constant can be used as an indicator to identify forged iron and cast iron. We plan to use the results as basic data and to extend our study towards a systematic nondestructive measurement of iron cultural heritage.

  216. TRUST LiCAFと波長シフトファイバーを用いた2次元中性子イメージングセンサーの開発

    瓜谷章、山崎拓弥、渡辺賢一、山﨑淳、井口哲夫、福田健太郎、柳田健之       

    平成27年度中性子イメージング専門研究会プログラム 

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    Event date: 2016.1

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学原子炉実験所 事務棟大会議室   Country:Japan  

    平板状のTRUST LiCAF内部に、多数本の波長シフトファイバーをXY方向に配列させて作製した2次元中性子イメージングセンサーの諸特性について報告する。

  217. Upgrade of Neutron Energy Spectrometer with Onion-like Single Bonner Sphere Using TRUST Eu:LiCAF Scintillator

    T. Mizukoshi, K. Watanabe, A. Uritani, A. Yamazaki, T. Iguchi, T. Ogata, T. Muramatsu, T. Matsumoto, A. Masuda

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    Event date: 2015.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    In order to measure neutron energy spectra, the conventional Bonner Sphere Spectrometers (BSS) are widely used. Operators should place these spheres in several times to a measurement point where radiation dose might be relatively high. In order to reduce this effort, novel neutron energy spectrometer using an onion-like single Bonner sphere was proposed in our group. This Bonner sphere has multiple sensitive spherical shell layers in the single sphere. In this spectrometer, a band-shaped thermal neutron detection medium, which consists of a LiF-ZnS mixed powder scintillator sheet and a wavelength-shifting (WLS) fiber readout, was looped to each sphere at equal angular intervals. Amount of LiF neutron converter is reduced near polar region in order to uniform the directional sensitivity. The LiF-ZnS mixed powder has an advantage of extremely high light yield. However, since it is opaque, this type of detector shows no characteristic shape in the pulse height spectrum. Subsequently, it is difficult to set the pulse height discrimination level. In order to solve this problem, we propose to replace the LiF-ZnS mixed powder into a flexible and Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST Eu:LiCAF) scintillator (Fig. 1). TRUST Eu:LiCAF scintillator can show a peak shape corresponding to neutron absorption events in the pulse height spectrum.
    We fabricated the prototype detector with five sensitive layers using TRUST LiCAF scintillator and conducted basic experiments to evaluate the directional uniformity of the sensitivity. The fabricated detector shows excellent directional uniformity of the neutron sensitivity (Fig.2).

  218. Development of position sensitive neutron detector using Transparent RUbber SheeT (TRUST) LiCaAlF6 neutron scintillator with wavelength-shifting fiber

    T. Yamazaki, K. Watanabe, A. Yamazaki, A. Uritani, T. Iguchi, T. Yanagida

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    Event date: 2015.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Development of alternatives to He-3 neutron detectors are required due to a He-3 shortage problem and increase in demand for neutron detectors in security and scientific applications. We have, therefore, developed a Transparent RUbber SheeT type Eu: LiCaAlF6 (TRUST LiCAF) neutron scintillator. This scintillator can easily be fabricated with a large area. For large area scintillators, wavelength-shifting(WLS) fiber readout is quite useful. The WLS fibers can also be inserted into a scintillator. The WLS fibers can absorb scintillation photons from the TRUST LiCAF and re-emit wavelength-shifted photons. In this paper, we demonstrate a neutron imaging using the TRUST LiCAF. We also evaluate the basic property.
    Figure 1 shows schematic views of the neutron-detecting head. The also WLS fibers are arranged at a regular pitch of 2.0 mm in the x and y directions. The light photons re-emitted in the WLS fifbers propagate through itself to the 64-channel multianode PMTs that are connected at one side of each fiber. Figure 2 shows examples of neutron images acquired with the TRUST LiCAF scintillator and object made of a cadmium sheet. The incident position of a neutron is calculated by the center of gravity algorithm. The object was located in front of the neutron-detecting head. We successfully demonstrated that the TRUST LiCAF scintillator can acquire neutron images. As future works, we will evaluate the spatial resolution and other important properties.

  219. Basic study on LET dependence of optical fiber type small size dosimeters using radiation-induced phosphor in 290 MeV/u carbon ions

    Yuho HIRATA, Kenichi WATANABE, Akira URITANI, Atsushi YAMAZAKI, Yusuke KOBA, Naruhiro MATSUFUJI, Takayuki YANAGIDA, Kentaro FUKUDA

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    Event date: 2015.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Heavy ion therapy can form fine dose distribution and irradiate only a target organ. Although fine dose distribution can reduce undesired irradiation into normal organs, misalignment of an irradiation position may cause significant accidental exposure. In order to estimate the irradiation dose accurately, dosimeters are required to be inserted into an affected region in a patient body. We, therefore, have developed a small size dosimeter consisting of an optical fiber and a radiation-induced phosphor. This phosphor shows quenching effect when irradiated with high linear energy transition (LET) particles. In this paper, we discuss this LET dependence of luminescence dosimeters irradiated with 290 MeV/u carbon ions.
    We fabricated the small size dosimeters with three phosphors, which were Eu:BaFBr, Ce:CaF2 and Bi4Ge3O12 (BGO). Carbon ions were irradiated into the fabricated dosimeters at Heavy Ion Medical Accelerator in Chiba (HIMAC). Fabricated dosimeters were set behind the water equivalent acrylic phantom. An ion chamber was also placed near the fabricated dosimeters as a reference.
    Figure 1 shows the depth profiles of the luminescence signal intensities, which is observed by changing the phantom thickness. Fabricated dosimeters show a Bragg peak at the same position as the ion chamber. Luminescence efficiencies were decreased as a function of LET as shown in Figure 2. There is a difference in the reduction coefficient in the LET dependence of these phosphors luminescence efficiencies. We corrected the LET dependence of the luminescence efficiency with this difference. The corrected depth profile is shown in Figure 1.

  220. Basic Study on Luminescence Property of Ho-doped Oxide Crystals

    Yosuke Kumagai, Kenichi Watanabe , Akira Uritani , Atsushi Yamazaki, Takayuki Yanagida

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    Event date: 2015.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    In radiation therapy which is one of remedy for cancer, it is important to enhance dose concentration to the diseased part. Particularly, we can form the extremely precise dose distribution in the ion beam radiotherapy, however, it is requested to improve the dose measurement technique for a guarantee on precise distribution. Therefore our group is advancing a development of small dosimeter that photostimulable phosphor is arranged on tip of an optical fiber. However photostimulable phosphors cause optically quenching in high LET radiation (heavy ion radiation). There are needed to be corrected LET effect for estimating accurate dose because these responses of the phosphor depend on not only dose but LET. We found the feasibility that correct LET effect by comparing responses of some phosphors which have each different response for LET effect. Therefore, various photostimulable phosphors are studied about LET effect evaluation. In this paper we discuss Ho-doped oxide crystal as new photostimulable and report its excitation and luminescence mechanism.

  221. Study on Radiation Damage for TlBr Semiconductor Radiation Detectors

    Motohiro Matsumura, Kenichi Watanabe, Atsushi Yamazaki, Akira Uritani, Nobumichi Nagano, Keitaro Hitomi

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    Event date: 2015.12

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Thallium bromide (TlBr) is one of attractive compound semiconductors for gamma-ray spectroscopy. The TlBr has the high stopping power which originates from its high atomic numbers (Tl=81, Br=35) and high density (7.56 g/cm3). The TlBr detector operates at room temperature because of the wide band-gap energy of 2.68 eV. The mobility-lifetime (μτ) products in TlBr crystals are respectively comparable to those for CdTe crystals.
    Recently crystal-growth methods have been improved. Consequently it is reported that TlBr detector achieves resolution of < 1.0%. In order to show such a high performance, TlBr become one of the detectors which have high energy resolution and high detection efficiency at room-temperature for use in medicine and engineering. However, TlBr is still under development. The basic properties, such as the energy resolution and the peak to Compton ratio, have been examined. On the other hand, some important properties of TlBr in the practical stage are kept untouched. One of these problems is radiation hardness. If TlBr detectors have very low radiation hardness, it is deep problem for practical application. If TlBr detectors have high radiation hardness, TlBr stably operates in high dose rate field as one of the new application of TlBr detectors.
    In this paper, we show a radiation hardness of TlBr semiconductor detectors for gamma-ray. We irradiated TlBr with gamma-ray emitted from 60Co (36.2 TBq). Total irradiation time is 24 hours. The radiation hardness has been observed using spectra and μτ products of electrons at interval of irradiation and after irradiation. The spectroscopic performance of TlBr detector for 137Cs was estimated at room temperature. Figure 1 shows that the ratios of peak channel are constant. Figure 2 shows that the spectrum shape isn't distorted after exposures. We confirm that the TlBr semiconductor detectors have strong resistance for gamma-ray.

  222. Neutron Energy Spectrometer Using Onion-like Single Moderator Sphere

    Akira URITANI, Tomoaki MIZUKOSHI, Kenichi WATANABE, Atsushi YAMAZAKI

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    Event date: 2015.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  223. Neutron Flux Monitoring and Calibration of the Neutron Detectors in LHD

    A. Uritani, Y. Nakano, M. Isobe, K. Ogawa, T. Nishitani, K. Watanabe and A. Yamazaki

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    Event date: 2015.11

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  224. Novel Digital Signal Processing Technique for TlBr Semiconductor Detector International conference

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    Event date: 2015.10 - 2015.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    The TlBr detector shows high gamma-ray detection efficiency because of its high atomic numbers and high density. However, the TlBr planer detector with more than 1mm thick can hardly operate with high energy resolution because the mobility-lifetime product (µt) of holes is not so high. In order for the sensitivity of the TlBr to be further improved, a thicker detector is required to be realized. In order to effectively read out the information of deposition energy in the TlBr detector, we study a novel digital signal processing technique. In conventional detectors, induced charges are accumulated for sufficient time to collect whole carrier information. However, in detectors with low carrier mobility, slow carriers, such as holes, may be captured before achieving to electrodes. One of the methods to eliminate information of slow carriers is a single polarity charge sensing technique, such as Frisch grid detector. For TlBr detector, capacitive Frisch grid technique was applied and excellent energy resolution was achieved. However, capacitive Frisch grid type detectors show asymmetric peak shape because of its imperfection in single polarity charge sensitivity. In this paper, we propose a novel digital signal processing technique extracting information of early carrier movement before carriers are captured. The increase rate of induced charges, or induced current, in a planner detector consisting of parallel plate electrodes is proportional to the total produced charge because carrier velocity and weighting potential are constant. The induced current in early period of a signal pulse is proportional to total produced charge or deposition energy. In order to confirm the feasibility of our proposed technique, we conducted basic experiments. We confirm that the induced current spectrum shows clearer and more symmetric peak shape than the conventional pulse height spectrum.

  225. Characterization of Neutron Energy Spectrometer With Onion-like Single Bonner Sphere Using TRUST LiCAF Scintillator International conference

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    Event date: 2015.10 - 2015.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Novel neutron energy spectrometer using an onion-like single Bonner sphere was proposed in our group. This Bonner sphere has multiple sensitive spherical shell layers in the single sphere and can obtain information for estimation of a neutron energy spectrum in one measurement. In this spectrometer, a band-shaped thermal neutron detection medium, which consists of a LiF-ZnS mixed powder scintillator sheet and a wavelength-shifting (WLS) fiber readout, was looped to each sphere at equal angular intervals. However, since the LiF-ZnS mixed powder scintillator shows no characteristic shape in the pulse height spectrum, it is difficult to set the pulse height discrimination level. In order to solve this problem, we replaced the LiF-ZnS mixed powder into a flexible and Transparent RUbber SheeT type LiCaAlF6 (TRUST LiCAF) scintillator. TRUST LiCAF scintillator can show a peak shape corresponding to neutron absorption events in the pulse height spectrum. To uniform the directional sensitivity, an amount of LiCAF neutron converter is reduced near polar region, where the detector media are concentrated. We fabricated the prototype detector with five sensitive layers using TRUST LiCAF scintillator. In this paper, we characterize the fabricated detector. We check the directional uniformity and the neutron energy dependence of the detector sensitivity. The detector shows excellent directional uniformity in the neutron sensitivity. We confirmed that the measured energy response, which was evaluated at monoenergetic neutron sources, agrees with the simulated one, which was calculated by Monte Carlo simulation code PHITS.

  226. Correction of LET Dependence of an Optical Fiber Type Small OSL Dosimeter International conference

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    Event date: 2015.10 - 2015.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Heavy ion therapy can form fine dose distribution and irradiate only a target organ. Although fine dose distribution can reduce undesired irradiation into normal organs, misalignment of an irradiation position may cause significant accidental exposure and/or deficiency of the irradiation dose into a tumor. In order to accurately estimate the irradiation dose, dosimeters are required to be inserted into an affected region in a patient body. We, therefore, have developed a small size dosimeter consisting of an optical fiber and an optically stimulated luminescence (OSL). This dosimeter can read out OSL signals through the optical fiber when irradiated with a stimulation laser. However, the OSL materials show quenching effect when irradiated with high linear energy transition (LET) particles. In this paper, we discuss the correction of LET dependence of small OSL dosimeters. We fabricated two types of small size dosimeters using different OSL materials, Eu:BaFBr and Ce:CaF2. Carbon ions were irradiated into the fabricated dosimeters at Heavy Ion Medical Accelerator in Chiba (HIMAC). The small size dosimeters were set behind the water equivalent acrylic phantom. We confirmed the luminescence efficiencies of Eu:BaFBr and Ce:CaF2 decrease with the LET. The ratio of the luminescence intensities between Eu:BaFBr and Ce:CaF2 also reduces as a function of the LET. We can obtain the LET value from this relation and then determine the luminescence efficiency of each dosimeter. We, therefore, can correct the LET dependence of the luminescence efficiency.

  227. Development of One-Dimensional Wide X-Ray Line Sensor with a Parallel Plate Collimator for Backscattered X-Ray Inspection International conference

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    Event date: 2015.10 - 2015.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Nondestructive internal inspections with imaging function are quite useful for large structures. Although a transmission X-ray imaging technique has high spatial resolution, it is unsuitable for large size structures because it is necessary to sandwich an object between an X-ray source and detectors. The backscattered X-ray imaging technique can be used for the internal visualization of large size structures because it can inspect from one-side of an object. Conventional backscattered X-ray inspection is conducted by two-dimensionally scanning a relatively low-energy pencil-beam X-ray, in which a rotating collimator is used for one-dimensional scanning. Higher energy X-ray is preferable to take an internal image of a large object because higher energy X-ray has higher penetration ability. However, pencil-beam scanning of high energy X-ray requires a heavy and large rotating collimator for beam shaping and scanning. We, therefore, proposed another approach, in which an X-ray beam is shaped into a fan-beam and a detector is one-dimensional position sensitive, for inspection of large size structures. Our detector has parallel plate collimator perpendicular to the plane of the fan-beam X-ray in order to define X-ray scattering positions. In this technique, we can obtain a one-dimensional backscattered X-ray profile in one measurement. We can conduct two-dimensional imaging by scanning only in one direction. The proposed system requires no heavy rotating collimator. In this paper, we fabricated the prototype detector and conducted basic experiments to confirm the feasibility of the proposed technique. We acquired the backscattered X-ray line profiles from a concrete slab object, when irradiating 950 keV linac X-rays. The acquired line profiles have intense signals corresponding to object positions. As future works, we will make a two dimensional image by scanning in the perpendicular direction to the fan-beam plane.

  228. 鉄文化財の材料特性と製造方法解明のためのパルス中性子透過法による鉄鋼材料研究

    磯野真理子、田中眞奈子、塩田佳徳、渡辺賢一、鬼柳善明、瓜谷章

    日本鉄鋼協会第170回秋季講演大会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:九州大学伊都キャンパス   Country:Japan  

  229. 臭化タリウム半導体検出器の耐放射線性

    松村 基広, 山崎 淳, 渡辺 賢一, 瓜谷 章, 長野宣道, 人見啓太朗

    第76回応用物理学会秋季講演会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  230. インフラ診断用後方散乱X 線イメージング装置の開

    豊川弘之,藤原健,萬代新一,伊佐英範,瓜谷章,渡辺賢一,山崎淳,遠山貴之,大橋和也,井上彬,夏井拓也,吉田光宏

    第76回応用物理学会秋季講演会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  231. 後方散乱X線イメージングのためのマルチスリットコリメータ付一次元X線ラインセンサの開発

    遠山貴之, 山﨑淳, 渡辺賢一, 瓜谷章, 豊川弘之, 藤原健, 萬代新一

    第76回応用物理学会秋季講演会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  232. パルス中性子ブラッグエッジ透過法と鉄鋼材料評価への応用

    磯野真理子, 田中眞奈子, 塩田佳徳, 渡辺賢一, 鬼柳善明, 瓜谷章

    第76回応用物理学会秋季講演会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  233. Ho:YAP の光刺激蛍光に関する基礎研究

    熊谷洋祐, 渡辺賢一, 山﨑淳, 瓜谷章, 柳田健之

    第76回応用物理学会秋季講演会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋国際会議場   Country:Japan  

  234. TRUST LiCAF を用いた多重球殻構造を有する単一減速材球型中性子スペクトロメータ

    水越友亮,瓜谷章,渡辺賢一,山﨑淳,村松貴史,尾方智洋

    日本原子力学会「2015年秋の大会」 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:静岡大学静岡キャンパス   Country:Japan  

  235. 名古屋大学における加速器BNCT 用システム開発;(2)中性子減速体の設計

    校條洋輔,瓜谷章,山崎淳,渡辺賢一,広田克也,北口雅暁,清水裕彦,市川豪,鬼柳善明,土田一輝

    日本原子力学会「2015年秋の大会」 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:静岡大学静岡キャンパス   Country:Japan  

  236. 名古屋大学における加速器BNCT 用システム開発;(1)計画概要と加速器について

    瓜谷章,校條洋輔,山﨑淳,渡辺賢一,市川豪,広田克也,北口雅暁,清水裕彦,鬼柳善明,土田一輝

    日本原子力学会「2015年秋の大会」 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:静岡大学静岡キャンパス   Country:Japan  

  237. 光刺激蛍光体のLET 依存性に関する検討

    平田悠歩,瓜谷章,渡辺賢一,山﨑淳,古場裕介,松藤成弘

    日本原子力学会「2015年秋の大会」 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:静岡大学静岡キャンパス   Country:Japan  

  238. 名古屋大学における加速器BNCT 用中性子源の開発 ―開発計画と加速器について―

    土田 一輝、鬼柳 善明、瓜谷 章、渡辺 賢一、山崎 淳、校條 洋輔、辻 義之、清水 裕彦、北口 雅暁、広田 克也、市川 豪

    第12回日本中性子捕捉療法学会学術大会 

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    Event date: 2015.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:神戸学院大学 ポートアイランドキャンパス   Country:Japan  

  239. 高エネルギーX 線源を用いた後方散乱X 線によるコンクリート等の片面からの内部検査手法の開発

    豊川弘之, 藤原健,萬代新一,伊佐英範,瓜谷章, 渡辺賢一, 山崎淳, 遠山貴之

    平成27年度非破壊検査総合シンポジウム 

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    Event date: 2015.6

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:(一社)日本非破壊検査協会 亀戸センター   Country:Japan  

    後方散乱X線イメージングは、X線透過試験が適用できない複雑な形状の構造物や、足場の悪い現場、内部構造が不明の建造物でも、片側からのアクセスで内部を可視化することができる。そのため、現場での検査の効率化と高精度化が期待できる。我々は電子加速器技術を用いた高エネルギーX線発生装置と、一次元マルチスリットX線検出器を用いた後方散乱イメージングシステムを合わせて開発している。開発状況について報告する。

  240. マルチスリット付一次元広幅X 線ラインセンサの開発

    遠山貴之,瓜谷章,渡辺賢一,山﨑淳,豊川弘之

    日本原子力学会 2015年春の年会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学日立キャンパス   Country:Japan  

  241. 多層球殻型単一ボナー球中性子スペクトロメータの開発

    渡辺賢一,牛田雅人,水越友亮,山﨑淳,瓜谷章,井口哲夫, 尾方智洋,村松貴史

    日本原子力学会 2015年春の年会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学日立キャンパス   Country:Japan  

  242. モンテカルロ計算に基づくヘリカル型核融合実験装置の中性子モニタに関する研究(3);構造物の詳細検討

    仲野裕次,瓜谷章,渡辺賢一,山﨑淳,磯部光孝,小川国大

    日本原子力学会 2015年春の年会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学日立キャンパス   Country:Japan  

  243. コンクリート内部を可視化する後方散乱X線装置の開発

    豊川弘之,平義隆,萬代新一,瓜谷章,渡辺賢一,藤原健

    第62回応用物理学会春季学術講演会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学湘南キャンパス   Country:Japan  

  244. TRUST LiCAFと波長シフトファイバを用いた中性子検出器の特性評価

    山崎拓弥, 杉本大, 渡辺賢一, 山﨑淳, 瓜谷章, 井口哲夫, 福田健太郎, 石津澄人, 柳田健之

    第62回応用物理学会春季学術講演会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学湘南キャンパス   Country:Japan  

  245. Ho添加酸化物結晶の放射線誘起発光特性に関する基礎研究

    熊谷洋祐, 渡辺賢一, 山崎淳, 瓜谷章, 柳田健之

    第62回応用物理学会春季学術講演会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学湘南キャンパス   Country:Japan  

  246. TRUST LiCAFと波長シフトファイバを使用した中性子イメージング検出器の開発

    杉本大, 山崎拓弥, 渡辺賢一, 山﨑淳, 瓜谷章, 井口哲夫, 福田健太郎, 石津澄人, 柳田健之

    第62回応用物理学会春季学術講演会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東海大学湘南キャンパス   Country:Japan  

  247. 加速器BNCTシステムにおける中性子輸送計算関する研究

    校條洋輔, 瓜谷章, 鬼柳善明, 土田一輝, 渡辺賢一

    研究会「放射線検出器とその応用」 (第29回) 

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    Event date: 2015.2

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:高エネルギー加速器研究機構   Country:Japan  

  248. マルチスリット付一次元広幅X線ラインセサの開発

    遠山貴之, 山崎淳, 渡辺賢一, 瓜谷章, 豊川弘之

    研究会「放射線検出器とその応用」 (第29回) 

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    Event date: 2015.2

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:高エネルギー加速器研究機構   Country:Japan  

  249. Ho添加酸化物のシンチレーションおよびOSL発光特性に関する基礎研究

    熊谷洋祐, 渡辺賢一, 山崎淳, 瓜谷章, 柳田健之

    研究会「放射線検出器とその応用」 (第29回) 

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    Event date: 2015.2

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:高エネルギー加速器研究機構   Country:Japan  

  250. TRUST LiCAFと波長シフトァイバを用いた中性子検出器の特評価

    山﨑拓弥, 杉本大, 渡辺賢一, 山﨑淳, 瓜谷章, 井口哲夫, 福田健太郎, 石津澄人, 柳田健之

    研究会「放射線検出器とその応用」 (第29回) 

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    Event date: 2015.2

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:高エネルギー加速器研究機構   Country:Japan  

  251. LHD Fusion Products Diagnostics International conference

    M. Isobe, K. Ogawa, T. Kobuchi, H. Miyake, H. Hayashi, H. Tomita, K. Watanabe, E. Takada, A. Uritani, J.H. Kaneko, S. Murakami, and Y. Takeiri

    A3 Foresight Program Workshop on Critical Physics Issues Specific to Steady State Sustainment of High-Performance Plasmas 

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    Event date: 2015.1

    Language:English   Presentation type:Oral presentation (general)  

    Country:China  

  252. 放射線誘起蛍光体とファイバを用いた小型量計の応答評価

    平田悠歩,渡辺賢一, 山﨑淳, 瓜谷章, 古場裕介,松藤成弘

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  253. 臭化タリウム半導体検出器の新しい信号処理法に関する研究

    松村基広 , 山﨑淳 , 渡辺賢一 , 瓜谷章, 人見啓太郎

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  254. 炭素量の異なる鉄鋼材料のパルス中性子を用いた透過率測定とブラッグエッジ解析 International conference

    磯野 真理子、塩田 佳徳、渡辺 賢一、瓜谷 章、鬼柳 善明、 田中 眞奈子

    日本中性子科学会第14回年会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学   Country:Japan  

  255. Neutron Detection Property of Small Scintillators Dispersed in Transparent Resin (TRUST LiCAF)

    A. Uritani, D. Sugimoto, T. Yamazaki, T. Mizukoshi, K. Watanabe, A. Yamazaki, K. Fukuda, S. Ishizu, N. Kawaguchi, Y. Fujimoto, K. Yanagida, A. Yoshikawa

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  256. Stereographic Backscattered X-Ray Tomography with Scanning Pencil-Beam for One-Sided Nondestructive Inspection International conference

    T. Tohyama, A. Yamazaki, K. Watanabe, A. Uritani

    IEEE NUCLEAR SCIENCE SYMPOSIUM 

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    Event date: 2014.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Routine maintenance and inspections for large size infrastructure, such as bridges and tunnels, are required due to aging degradation. The nondestructive internal inspection with imaging is quite useful for this purpose. Although the transmission X-ray imaging technique has high spatial resolution, it is unsuitable for large size structures because it is necessary to sandwich objects between an X-ray source and detectors. The backscattered X-ray imaging technique can be used for the internal visualization of large size structures because it can carry out an inspection from one-side of the object. However, it takes long time to obtain a tomographic image based on this technique. Therefore, we proposed a tomography technique based on backscattered X-ray, which is available for large size structures and reduces measurement time, as a one-sided inspection. The proposed system consists of a pencil-beam X-ray source, which can sweep an angle and slide a position, and the X-ray detectors which record the integrated quantity of the backscattered X-rays for every incident angles and source positions. The recorded values are indexes of the line integral of scattering cross section along the incident X-ray beam. Tomographic images can be acquired using image reconstruction procedures based on a stereographic technique. In this paper, we simulated the projection of backscattered X rays using the Monte Carlo simulation code EGS5 to confirm the principle of our tomographic imaging technique. We successfully demonstrated that the stereographic backscattered X-ray tomography was able to reconstruct the tomographic image of the object shape with one-sided inspection. In addition, we experimentally confirmed that a sufficient amount of backscattered X-ray can be acquired.

  257. Characterization of Large Area Transparent RUbber SheeT (TRUST) LiCaAlF6 Neutron Scintillator International conference

    K. Watanabe, A. Yamazaki, D. Sugimoto, T. Yamazaki, A. Uritani, T. Iguchi, K. Fukuda, S. Ishidu, T. Yanagida, Y. Fujimoto

    IEEE NUCLEAR SCIENCE SYMPOSIUM 

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    Event date: 2014.11

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

    Alternatives of standard He-3 neutron detectors have been required to be developed because of the He-3 shortage. We are developing the Eu:LiCaAlF6 scintillators as one of the candidates for an alternative of the He-3 detector. Although this scintillator has high light yield, it suffers from the interference of gamma rays due to its relatively low a/ß ratio. In addition, synthesis of large Eu:LiCaAlF6 single crystals requires relatively long time and high cost. In order to solve these problems, we have developed a Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST LiCAF) scintillator in which small pieces of Eu:LiCaAlF6 scintillators are dispersed. The size of small pieces of Eu:LiCaAlF6 crystals are controlled to be smaller than the ranges of fast electrons induced by gamma rays and larger than the ranges of alphas and tritons produced by 6Li(n,t) reaction. Consequently, the signal pulse height of gamma-ray induced events can be reduced smaller than that of neutron induced events. The size or area of this type of scintillator can easily be enlarged using a large size mold in the solidification process of the resin. In this paper we fabricated a relatively large size TRUST LiCAF scintillator and evaluated its basic performances. The TRUST LiCAF scintillator was directly mounted on the window of the photomultiplier tube. Gamma-ray induced events are almost completely eliminated by setting an adequate threshold level. Consequently, sufficiently low gamma-ray detection efficiency was confirmed with keeping adequate neutron detection efficiency.

  258. Gamma-Ray Suppression with Pulse Shape Discrimination Technique for Transparent RUbber SheeT (TRUST) LiCaAlF6 Neutron Scintillator with Wavelength-Shifting Fiber Readout International conference

    T. Yamazaki, K. Watanabe, A. Yamazaki, D. Sugimoto, A. Uritani, T. Iguchi, K. Fukuda, S. Ishidu, T. Yanagida

    IEEE NUCLEAR SCIENCE SYMPOSIUM 

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    Event date: 2014.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Alternatives to He-3 neutron detectors are required to be developed due to He-3 shortage problem and increase in demand for neutron detectors in security and scientific applications. We have, therefore, developed a Transparent RUbber SheeT type Eu:LiCaAlF6 (TRUST LiCAF) neutron scintillator. This type of scintillator is made of a transparent rubber sheet in which a large number of small pieces of Eu:LiCaAlF6 scintillator are dispersed. In the TRUST LiCAF scintillator, pulse heights of gamma-ray induced events are suppressed and these events can easily be rejected with pulse height discrimination. In addition, this scintillator can easily be fabricated with large area. For large area scintillators, wavelength-shifting fiber (WLS) fiber readout is quite useful. In this paper, we evaluated the basic performance of the TRUST LiCAF scintillator with WLS fiber readout. WLS fibers were bundled in plate shape. The TRUST LiCAF scintillator with the size of 200x50x5 mm3 was mounted on the WLS fiber plate. Although the peak shape corresponding to the neutron absorption events can clearly be confirmed, gamma-ray induced events also have relatively high pulse heights. These events with relatively high pulse heights is considered to be events produced in the WLS fiber by interactions between gamma rays and the WLS fibers. The scintillation in the WLS fiber has shorter decay time of a few ns compared with the TRUST LiCAF scintillator whose decay time is a few µs. Fiber emission events can be clearly distinguished from TRUST LiCAF scintillator emission events by using the pulse shape discrimination technique. Consequently, gamma-ray detection efficiency can sufficiently be reduced with keeping adequate neutron detection efficiency.

  259. Development of a Novel Neutron Energy Spectrometer Using Onion-like Multi-Shell Single Bonner Sphere International conference

    K. Watanabe, M. Ushida, A. Yamazaki, A. Uritani, T. Iguchi, T. Ogata, T. Muramatsu

    IEEE NUCLEAR SCIENCE SYMPOSIUM 

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    Event date: 2014.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    In order to measure neutron energy spectra, the conventional Bonner Sphere Spectrometers (BSS) are widely used. The neutron spectrum can be derived by deconvolution procedures, which reconstruct the spectrum from several Bonner spheres outputs by using their response functions. In this spectrometer, since several measurements with different Bonner spheres are required, operators should bring these spheres many times to the measurement point where the radiation dose might be relatively high. In order to solve this disadvantage, a single Bonner sphere that utilizes difference in spatial distribution of the thermal neutrons in the sphere was proposed. Since the conventional single Bonner sphere spectrometers consist of some small thermal neutron detectors discretely arranged in the sphere or three one-dimensional position sensitive counters perpendicularly arranged, they have considerable directional dependence in the detector response. We have, therefore, proposed a novel neutron energy spectrometer using an onion-line single Bonner sphere, which has multiple sensitive spherical shells as the detector configuration without directional dependence. In this paper, in order to confirm the detector response of the proposed neutron spectrometer, the prototype detector with five sensitive layers was fabricated and basic experiments were carried out. The experimental results are consistent with the expected c simulated with Monte Carlo calculations. The count rates of outer layers increase and the rates of inner layers decrease compared with the direct irradiation condition in which the neutron spectrum is harder. We experimentally confirmed the detector response which reflects the neutron energy spectrum.

  260. Study on Neutron Imaging Technique Using Transparent RUbber SheeT (TRUST) LiCaAlF6 Neutron Scintillator International conference

    D. Sugimoto, K. Watanabe, A. Yamazaki, T. Yamazaki, A. Uritani, T. Iguchi, K. Fukuda, S. Ishidzu, T. Yanagida

    IEEE NUCLEAR SCIENCE SYMPOSIUM 

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    Event date: 2014.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    We have developed Eu:LiCaAlF6 (Eu:LiCAF) scintillators as a novel He-3 alternative neutron detector. Although this scintillator has various useful properties such as high neutron detection efficiency, high light yield, no hygroscopicity and high transparency, it suffers from the influence of gamma-ray due to its low a/ß ratio. In addition, single crystal scintillators are generally difficult to fabricate detectors with a large area of several tens of square centimeters. To overcome these difficulties, we proposed to disperse small pieces of Eu:LiCAF scintillators into a transparent rubber and form a rubber sheet type scintillator. This type of scintillator is referred to as a Transparent RUbber SheeT (TRUST) LiCAF scintillator. A small piece of Eu:LiCAF scintillator can selectively reject only gamma-ray events due to a difference between ranges of fast electrons induced by gamma rays and 6Li(n,t) reaction products. By dispersing small pieces of Eu:LiCAF crystals into a transparent rubber sheet, the neutron detection efficiency can increase with keeping the gamma-ray event suppression ability. Since a TRUST LiCAF scintillator can easily enlarged its area, a neutron imaging is one of the attractive applications. In this paper, we successfully demonstrate that the TRUST LiCAF scintillator can acquire neutron images. Under the current status, the spatial resolution is evaluated to be less than a few mm.

  261. 赤外発光シンチレータを用いた耐放射線性の高い放射線検出器の開発

    熊谷洋祐,渡辺賢一,山崎 淳,瓜谷 章

    第75回応用物理学会秋季学術講演会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学   Country:Japan  

  262. Eu:LiCaAlF6分散樹脂型シンチレータの発光特性の評価

    杉本大,山﨑拓弥,渡辺賢一,山﨑淳,瓜谷章,井口哲夫,福田健太郎,石津澄人,柳田健之

    第75回応用物理学会秋季学術講演会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学   Country:Japan  

  263. 透明樹脂型Eu:LiCaAlF6シンチレータと波長シフトファイバ読出しを用いた大面積中性子検出器の開発

    山﨑拓弥,杉本大,渡辺賢一,山﨑淳,瓜谷章,井口哲夫,福田健太郎,石津澄人,柳田健之

    第75回応用物理学会秋季学術講演会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:北海道大学   Country:Japan  

  264. モンテカルロ計算に基づくヘリカル型核融合実験装置の中性子モニタに関する研究(2)モニタ設置位置の検討

    仲野裕次,瓜谷章,渡辺賢一,山﨑淳,磯部光孝,小川国大

    日本原子力学会 2014年秋の大会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学吉田キャンパス   Country:Japan  

  265. LIBS を用いた固体表面水素分布測定法に関する研究

    吉本久晃,瓜谷章,渡辺賢一,山﨑淳,井上龍夫

    日本原子力学会 2014年秋の大会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学吉田キャンパス   Country:Japan  

  266. 後方散乱X 線断層撮像技術に関する研究

    ○遠山貴之,瓜谷章,渡辺賢一,山﨑淳,吉田迅

    日本原子力学会 2014年秋の大会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:京都大学吉田キャンパス   Country:Japan  

  267. Project of Electrostatic Accelerator-based BNCT System in Nagoya University

    Yoshiaki KIYANAGI, Kazuki TSUCHIDA , Akira URITANI, Yuya KAWABATA, Atsushi YAMAZAKI, Menjo Yosuke, Takuya YAMAZAKI, Kenichi WATANABE, Katsuya HIROTA, Masaaki KITAGUCHI, Hirohiko SHIMIZU

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    Event date: 2014.8

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  268. Development of an accelerator-driven compact neutron source for BNCT in Nagoya University International conference

    K. Tsuchida, Y. Kiyanagi, A. Uritani, K. Watanabe, H. Shimizu, K. Hirota, M. Kitaguchi

    16th International Congress on Neutron Capture Therapy 

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:Finland  

    Development of an accelerator-driven compact neutron source has been started in Nagoya University for BNCT application based on a low-energy high-current DC accelerator, which has also extra possibilities of applications to fundamental physics experiments and industry uses.

  269. Fundamental properties of Transparent RUbber SheeT (TRUST) LiCaAlF6 neutron scintillator International conference

    Dai Sugimoto, A. Uritani et al.

    2014 Symposium on Radiation Measurements and Applications 

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  270. Response evaluation of a small radiation detector using OSL with optical fiber readout to high energy carbon ions International conference

    Dai Sugimoto, A. Uritani et al.

    2014 Symposium on Radiation Measurements and Applications 

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  271. Tomographic imaging from one-side using backscattered X-ray International conference

    K. Watanabe, A. Uritani et al.

    2014 Symposium on Radiation Measurements and Applications 

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  272. Wavelength-shifting fiber signal readout from Transparent Rubber SheeT (TRUST) type LiCaAlF6 neutron scintillator International conference

    K. Watanabe, A. Uritani et al.

    2014 Symposium on Radiation Measurements and Applications 

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  273. Wide dynamic range neutron flux monitor having fast time response for the Large Helical Device International conference

    M. Isobe, K. Ogawa, H. Miyake, H. Hayashi, T. Kobuchi, Y. Nakano, K. Watanabe, A. Uritani, T. Misawa, T. Nishitani, M. Tomitaka, T. Kumagai, Y. Mashiyama, D. Ito, S. Kono, M. Yamauchi and Y. Takeiri

    20th Topical Conference on High-Temperature Plasma Diagnostics  

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:United States  

    A fast time response, wide dynamic range neutron flux monitor has been developed toward the LHD deuterium operation by using leading-edge signal processing technologies, providing maximum counting rate up to ~5×109 (cps). Because a maximum total neutron emission rate over 1×1016 (n/s) is predicted in neutral beam-heated LHD plasmas, fast response and wide dynamic range capabilities of the system are essential. Preliminary tests have demonstrated successful performance as wide dynamic range monitor along the design.

  274. Study on in-situ calibration for neutron flux monitor in the Large Helical Device based on Monte Carlo calculations International conference

    Y. Nakano, A. Yamazaki, K. Watanabe, A. Uritani, K. Ogawa, M. Isobe

    20th Topical Conference on High-Temperature Plasma Diagnostics  

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:United States  

    Neutron monitoring is important to manage safety of fusion experiment facilities because neutrons are generated in fusion reactions. Monte Carlo simulations play an important role in evaluating the influence of neutron scattering from various structures and correcting differences between deuterium plasma experiments and in-situ calibration experiments. We evaluated influence based on differences between the both experiments at Large Helical Device using Monte Carlo simulation code MCNP5. A difference between the both experiments in absolute detection efficiency of the fission chamber between O-ports is estimated to be the biggest of all monitors. We additionally evaluated correction coefficients for some neutron monitors.

  275. 名古屋大学における加速器BNCT用システム開発

    瓜谷章、土田一輝、鬼柳善明、渡辺賢一、山﨑淳、清水裕彦、広田克也、北口雅暁、川端勇矢、山崎拓弥

    日本原子力学会 2014年春の年会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京都市大学 世田谷キャンパス   Country:Japan  

  276. モンテカルロ計算に基づくヘリカル型核融合実験装置の中性子モニタに関する研究

    仲野裕次,瓜谷章,渡辺賢一,山﨑淳, 磯部光孝,小川国大

    日本原子力学会 2014年春の年会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京都市大学 世田谷キャンパス   Country:Japan  

  277. 光刺激蛍光を用いた光ファイバ型放射線検出器の炭素イオンビームに対する応答評価

    渡辺賢一,宮前英史,山﨑淳,瓜谷章,古場裕介,松藤成弘

    日本原子力学会 2014年春の年会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:東京都市大学 世田谷キャンパス   Country:Japan  

  278. シンチレータを先端に配した光ファイバ型検出器による放射線治療時の線量モニタリングに関する基礎検討

    尾崎成彰 ,渡辺賢一,宮前英史,山﨑 淳,瓜谷 章,古場裕介,松藤成弘

    第61回応用物理学会春季学術講演会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:青山学院大学相模原キャンパス   Country:Japan  

  279. はじめに

    瓜谷 章

    第61回応用物理学会春季学術講演会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:青山学院大学相模原キャンパス   Country:Japan  

    シンポジウム「放射線・粒子シミュレータの最新動向」のイントロダクション

  280. レーザー駆動陽子線加速における加速性能向上に向けた基礎特性評価

    吉本久晃,山﨑 淳,渡辺賢一,瓜谷 章,井上龍夫

    第61回応用物理学会春季学術講演会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:青山学院大学相模原キャンパス   Country:Japan  

  281. 光刺激蛍光を用いた光ファイバー型小型線量計の実用化に向けた詳細検討

    宮前英史,渡辺賢一,山﨑 淳,瓜谷 章,松藤成弘,古場裕介

    第61回応用物理学会春季学術講演会 

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    Event date: 2014.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:青山学院大学相模原キャンパス   Country:Japan  

  282. モンテカルロ計算に基づくヘリカル型核融合実験装置の中性子モニタリングシステムの検討

    仲野裕次,渡辺賢一,山﨑淳,瓜谷章,磯部光孝,小川国大

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  283. レーザー駆動陽子線加速における加速性能向上に関する基礎検討

    吉本久晃,渡辺賢一,山﨑淳,瓜谷章,井上龍夫

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  284. パルス幅可変レーザーの製作とレーザーアブレーション特性のパルス幅依存性

    酒井史人,渡辺賢一,山﨑淳,瓜谷章,井上龍夫

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  285. 極小LiCaAlF6シンチレータを光ファイバ先端に配したBNCT用中性子モニタの開発

    川端勇矢,渡辺賢一,山﨑淳,瓜谷章,井口哲夫,河口範明,福田健太郎,石津澄人,柳田健之,吉川彰

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  286. 重元素を含む蛍光体の蛍光感度のファントム中設置位置依存性に関する研究

    尾﨑成彰,宮前英史,渡辺賢一,瓜谷章,山﨑淳

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  287. 後方散乱X線断層撮像による片側からの非破壊検査技術の開発

    吉田迅,山﨑淳,渡辺賢一,瓜谷章

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  288. シンポジウム開催にあたって

    瓜谷章

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  289. 多重球殻状検出器を配した一球型ボナーボール検出器の応答評価実験

    牛田雅人,渡辺賢一,山﨑淳,瓜谷章,村松貴史,尾方智洋,河原林順,富田英生,井口哲夫

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  290. 輝尽性蛍光体と光ファイバーを用いた小型線量計の重粒子線対する応答評価

    宮前英史,渡辺賢一,瓜谷章,山﨑淳,松藤成弘,古場裕介

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  291. 小片状LiCaAlF6シンチレータ分散樹脂を用いた中性子検出器の開発

    杉本大,渡辺賢一,山﨑淳,瓜谷章,福田健太郎,石津澄人,河口範明,藤本裕,柳田健之,吉川彰

    第74回応用物理学会秋季学術講演会 

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    Event date: 2013.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:同志社大学京田辺キャンパス   Country:Japan  

  292. Ce:LiCaAlF6シンチレータにおける中性子/ガンマ線波形弁別

    渡辺賢一,近藤良行,高橋嘉彦,山﨑淳,瓜谷章,井口哲夫,河口範明,福田健太郎,柳田健之,藤本裕,石津澄人,吉川彰

    第60回応用物理学会春季学術講演会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Poster presentation  

    Venue:神奈川工科大学   Country:Japan  

  293. LiCaAlF6結晶のシンチレーション高速成分の帰属

    越水正典,柳田健之,藤本裕,近藤良行,山崎淳,渡辺賢一,瓜谷章,岸本俊二,浅井圭介

    第60回応用物理学会春季学術講演会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (invited, special)  

    Venue:神奈川工科大学   Country:Japan  

  294. LiCaAlF6を用いた光ファイバ型BNCT中性子場モニタの開発

    川端勇矢,渡辺賢一,山﨑淳,瓜谷章,井口哲夫,河口範明,福田健太郎,石津澄人,柳田健之,吉川彰

    第60回応用物理学会春季学術講演会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:神奈川工科大学   Country:Japan  

  295. 放射線誘起蛍光体の蛍光感度のファントム中設置深さ依存性に関する研究

    尾崎成彰,宮前英史,渡辺賢一,瓜谷章,山﨑淳

    第60回応用物理学会春季学術講演会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:神奈川工科大学   Country:Japan  

  296. 透過/散乱複合CTで用いる平行平板コリメータの幾何形状に関する検討

    吉田迅,山﨑淳,渡辺賢一,瓜谷章

    第60回応用物理学会春季学術講演会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:神奈川工科大学   Country:Japan  

  297. 輝尽性蛍光体と光ファイバーを用いた小型線量計の線量計応答詳細評価

    宮前英史,渡辺賢一,山﨑淳,瓜谷章

    日本原子力学会 2013年春の年会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:近畿大学 東大阪キャンパス   Country:Japan  

  298. レーザー加速陽子を用いた核変換技術の概念検討;(2)モンテカルロシミュレーションによる概念検討

    渡辺賢一,山﨑淳,岩井千恵,瓜谷章,井上龍夫,上野祥樹

    日本原子力学会 2013年春の年会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:近畿大学 東大阪キャンパス   Country:Japan  

  299. レーザー加速陽子を用いた核変換技術の概念検討;(1)全体概要

    瓜谷章,渡辺賢一,山﨑淳,岩井千恵,井上龍夫,上野祥樹

    日本原子力学会 2013年春の年会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:近畿大学 東大阪キャンパス   Country:Japan  

  300. 多重球殻状検出器を配した一球型ボナーボール検出器の配置検討

    牛田雅人,渡辺賢一,山﨑淳,丸山秀典,川端勇矢,瓜谷章,河原林順,井口哲夫, 村松貴史,富田英生,尾形智洋

    日本原子力学会 2013年春の年会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:近畿大学 東大阪キャンパス   Country:Japan  

  301. 放射能計測技術の動向

    瓜谷章

    平成25年電気学会全国大会 

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    Event date: 2013.3

    Language:Japanese   Presentation type:Symposium, workshop panel (nominated)  

    Venue:名古屋大学   Country:Japan  

  302. レーザーと発光分光法を用いた微量元素分析の検討

    吉本 久晃、山崎 淳、渡辺 賢一、瓜谷 章

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  303. パルス幅可変レーザーの製作とレーザーアブレーション特性のパルス幅依存性評価

    酒井史人、渡辺賢一、山崎淳、瓜谷章、井上龍夫

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  304. ビーズ状LiCaAlF6シンチレータを用いた中性子検出器の開発

    杉本 大、山﨑 淳、渡辺 賢一、瓜谷 章

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  305. モンテカルロ計算に基づくヘリカル型核融合実験装置の中性子モニタリングに関する研究

    仲野裕次、渡辺賢一、瓜谷章、磯部光孝

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  306. 放射線誘起蛍光素子の阻止能依存性に関する研究

    尾﨑 成彰、 宮前 英史、 渡辺 賢一、 瓜谷 章、 山﨑 淳

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学VBL   Country:Japan  

  307. The plan of the Nagoya university accelerator-driven neutron source (NUANS)

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    Event date: 2012.12

    Language:Japanese   Presentation type:Poster presentation  

    Country:Japan  

  308. コンプトン後方散乱同時計数法の基礎特性

    高木 孝、渡辺賢一、山﨑 淳、瓜谷 章

    日本放射線安全管理学会第11回学術大会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:大阪大学吹田キャンパス コンベンションセンター   Country:Japan  

  309. Evaluation of Neutron/Gamma-Ray Sensitivity Ratio for LiCaAlF6 Scintillators International conference

    K. Watanabe, Y. Kondo, Y. Takahashi, A. Yamazaki, A. Uritani, T.Iguchi, N. Kawaguchi, T. Yanagida, Y. Fujimoto, K. Fukuda, S. Ishidu, A. Yoshikawa

    IEEE 2012 Nuclear Science Symposium and Medical Imaging Conference 

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    Event date: 2012.10 - 2012.11

    Language:English   Presentation type:Poster presentation  

    Country:United States  

  310. Electron Density Imaging Combining Transmission and Compton Scattered X-Ray CT Technique International conference

    J. Yoshida, A. Yamazaki, K. Watanabe, A. Uritani

    IEEE 2012 Nuclear Science Symposium and Medical Imaging Conference 

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    Event date: 2012.10 - 2012.11

    Language:English   Presentation type:Poster presentation  

    Country:United States  

  311. Development of an Optical Fiber Detector for Neutron Monitoring in Boron Neutron Capture Therapy International conference

    Y. Kawabata, K. Watanabe, S. Maruyama, A. Yamazaki, T. Iguchi, A. Uritani, A. Yoshikawa, T. Yanagida, Y. Fujimoto

    IEEE 2012 Nuclear Science Symposium and Medical Imaging Conference 

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    Event date: 2012.10 - 2012.11

    Language:English   Presentation type:Poster presentation  

    Country:United States  

  312. 輝尽性蛍光体と光ファイバーを用いた超小型線量計の特性評価試験

    宮前英史,渡辺賢一,山﨑淳,瓜谷章,有賀英司

    日本原子力学会 2012年秋の大会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:広島大学   Country:Japan  

  313. 原子炉内の熱外中性子の小型指向性中性子検出器による中性子方向分布計測(2)

    丸山秀典,渡辺賢一,山﨑淳,瓜谷章

    日本原子力学会 2012年秋の大会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:広島大学   Country:Japan  

  314. Ce:LiCaAlF6シンチレータにおける発光特性の添加物依存性

    近藤良行,山﨑淳,渡辺賢一,瓜谷章,井口哲夫,柳田健之,藤本裕,吉川彰

    日本原子力学会 2012年秋の大会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:広島大学   Country:Japan  

  315. 多重球殻状検出器を配した一球型中性子スペクトロメータについての開発

    牛田雅人,渡辺賢一,山﨑淳,丸山秀典,川端勇矢,瓜谷章,河原林順,富田英生,井口哲夫,(MHI) 村松貴史,尾形智洋

    日本原子力学会 2012年秋の大会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:広島大学   Country:Japan  

  316. 透過/ 散乱複合CT による電子密度分布イメージング法に関する研究

    吉田 迅,山﨑淳,渡辺賢一,瓜谷章

    第73回応用物理学会学術講演会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:愛媛大学   Country:Japan  

  317. 発光波長特性を用いた中性子/ ガンマ線弁別に関する研究

    高橋嘉彦,山﨑淳,渡辺賢一,瓜谷章,河口範明,福田健太郎,石津澄人,柳田健之,吉川彰

    第73回応用物理学会学術講演会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:愛媛大学   Country:Japan  

  318. シンチレータブロック積層型機能性コリメータガンマカメラの開発

    坂野大翔,渡辺賢一,山﨑淳,瓜谷章

    第73回応用物理学会学術講演会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:愛媛大学   Country:Japan  

  319. 後方散乱同時計測法における測定パラメータに関する検討

    高木孝,渡辺賢一,山﨑淳,瓜谷章

    第73回応用物理学会学術講演会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:愛媛大学   Country:Japan  

  320. BNCT 中性子場モニタを目的とした光ファイバ型検出器の開発

    川端勇矢,丸山秀典,山﨑淳,渡辺賢一,瓜谷章,河口範明,福田健太郎,石津澄人,柳田健之,吉川彰

    第73回応用物理学会学術講演会 

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    Event date: 2012.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:愛媛大学   Country:Japan  

  321. BNCT 中性子場モニタリングを目的とした光ファイバ検出器の開発

    川端勇矢, 丸山秀典, 山﨑淳, 瓜谷章,渡辺賢一

    日本原子力学会 2012年春の年会 

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    Event date: 2012.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福井大学   Country:Japan  

  322. 多重球殻状検出器を配した一球型ボナーボール検出器の開発

    牛田雅人, 渡辺賢一, 山﨑淳, 瓜谷章,丸山秀典, 川端勇矢

    日本原子力学会 2012年春の年会 

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    Event date: 2012.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:福井大学   Count