Updated on 2024/04/17

写真a

 
YOSHIHASHI Sachiko
 
Organization
Administrative Support Organizations Nuclear Material Control Facility Professor
Graduate School
Graduate School of Engineering
Title
Professor

Degree 1

  1. 博士(工学) ( 2001.3   大阪大学 ) 

Research Interests 5

  1. 加速器中性子源

  2. 核融合

  3. 放射線計測

  4. ホウ素中性子補足療法

  5. リチウム

Research Areas 4

  1. Energy Engineering / Nuclear engineering  / BNCT

  2. Energy Engineering / Nuclear fusion  / 核融合材料

  3. Energy Engineering / Nuclear engineering  / 放射線計測

  4. Energy Engineering / Nuclear fusion  / 液体金属流動

Current Research Project and SDGs 3

  1. 核融合炉開発に向けた加速器型中性子源の開発

  2. 核融合炉でコミッショニングに向けた誘導放射能の評価

  3. ホウ素中性子捕捉療法のための加速器型中性子源の開発

Research History 3

  1. Nagoya University   Associate professor

    2016.4

  2. Fukui University of Technology   Associate professor

    2015.4 - 2016.3

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    Country:Japan

  3. Osaka University   Assistant Professor

    2005.4 - 2015.3

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    Country:Japan

Education 1

  1. Osaka University   Graduate School, Division of Engineering

    - 2001.3

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    Country: Japan

Professional Memberships 4

  1. 日本中性子捕捉療法学会   正会員

  2. プラズマ・核融合学会   会員

  3. Atomic Energy Society of Japan

  4. The Laser Society of Japan

Committee Memberships 13

  1. 福井県原子力安全専門委員会   委員  

    2022.3   

  2. 文部科学省核融合科学技術委員会   原型炉開発総合戦略タスクホース委員  

    2020   

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    Committee type:Government

  3. 鳥取県原子力安全顧問   顧問  

    2018.11   

  4. 核燃料安全専門審査会   審査委員  

    2016.6   

  5. 原子炉安全専門審査会   審査委員  

    2016.6   

  6. プラズマ・核融合学会   男女共同参画委員会委員  

    2022   

  7. 国立研究開発法人日本原子力研究開発機構 分離変換技術研究専門部会   専門委員  

    2020   

  8. 国立研究開発法人科学技術研究開発機構 核融合中性子源専門部会   専門委員  

    2020   

  9. 近畿大学原子炉等利用共同研究委員会   委員  

    2019   

  10. 日本原子力学会   教育委員会委員  

    2018.10   

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    Committee type:Academic society

  11. プラズマ核融合学会編集委員会   委員  

    2017.7 - 2019.6   

  12. もんじゅ安全・改革検証委員会   委員  

    2015.8 - 2017.3   

  13. 日本原子力学会   ダイバーシティ推進委員会委員  

    2013.4   

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    Committee type:Academic society

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Awards 3

  1. ベストプレゼンター賞

    2017.9   第14回日本中性子捕捉療法学会  

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    Award type:Award from Japanese society, conference, symposium, etc.  Country:Japan

  2. プラズマ・核融合学会賞 技術進歩賞

    2016.11   プラズマ・核融合学会  

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    Country:Japan

  3. 第45回日本原子力学会賞 技術開発賞

    2015.3   日本原子力学会  

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    Country:Japan

 

Papers 104

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

    Honda Shogo, Yoshihashi Sachiko, Tomita Seinosuke, Tsuchida Kazuki, Kiyanagi Yoshiaki, Tsurita Yukio, Watanabe Kenichi, Yamazaki Atsushi, Uritani Akira

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

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

    DOI: 10.1016/j.nima.2022.167140

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  2. 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 )   2021.4

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    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:Journal of Instrumentation  

    Accelerator-driven neutron sources have been developed worldwide for boron neutron capture therapy (BNCT) instead of nuclear reactors. Nagoya University is currently developing a compact DC accelerator driven BNCT system using a sealed lithium (Li) target. The target receives a high heat load by a proton beam, and the heat then requires efficient removal. This study developed a high-efficiency heat removal technique that uses V-shaped staggered ribs on the heat removal side of the flow channels. We performed experiments using an electron beam to confirm the technique performance. The results showed double the heat removal performance compared to the smooth surface channel. The value expected to sufficiently remove 6.6 MW/m2 of heat load provided by the proton beam at the Nagoya University neutron source for BNCT.

    DOI: 10.1088/1748-0221/16/04/P04016

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  3. Neutron flux distributions in the Large Helical Device torus hall evaluated by an imaging plate technique in the first campaign of the deuterium plasma experiment

    Kobayashi Makoto, Tanaka Tomoyo, Nishitani Takeo, Ogawa Kunihiro, Isobe Mitsutaka, Motojima Gen, Kato Akemi, Yoshihashi Sachiko, Osakabe Masaki

    NUCLEAR FUSION   Vol. 59 ( 12 )   2019.12

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

    The global flux distributions for thermal, epithermal and fast neutrons in the torus hall of large fusion devices were experimentally evaluated for the first time in the Large Helical Device (LHD) using the activation foil method measured by the imaging plate and high-purity germanium detector. It turned out that the thermal neutrons were effectively absorbed by borated polyethylene blocks placed beneath the LHD. This should reduce the radioactivity of the floor and would be beneficial in maintaining a good environment for radiation workers. Uniform distributions of epithermal and fast neutrons were observed near the LHD. In particular, the significant decrease in fast neutron flux with increasing distance from the LHD, due to the fast energy loss of fast neutrons, was observed. The neutron flux distribution measurement, with rough energy discrimination based on the threshold energy of the neutron activation foil, allows us to estimate the spatial radiation dose rate, as well as the radioactivity in components in the torus hall. The prediction of the radioactivity in the concrete floor indicated that radioactive isotope 55Fe will be a dominant source of radioactivity in the concrete after the nine-year deuterium experiment campaign finishes.

    DOI: 10.1088/1741-4326/ab3d14

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

    Tanaka Tomoyo, Yoshihashi Sachiko, Kobayashi Makoto, Uritani Akira, Watanabe Kenichi, Yamazaki Atsushi, Nishitani Takeo, Ogawa Kunihiro, Isobe Mitsutaka

    FUSION ENGINEERING AND DESIGN   Vol. 146   page: 496 - 499   2019.9

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

    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

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

    Nishitani T., Yoshihashi S., Tanagami Y., Amano S., Uritani A., Kwon S., Kondo K., Kumagai K., Ochiai K., Sato S.

    Fusion Engineering and Design   Vol. 202   2024.5

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    Publishing type:Research paper (scientific journal)   Publisher:Fusion Engineering and Design  

    An accelerator-based neutron source powered by deuteron–Li (d–Li) reactions is among the most promising neutron sources for fusion materials irradiation facilities, such as IFMIF, IFMIF-DONES, and A-FNS. The yield estimation of neutrons and other particles is critical to the design of these facilities. Presently, the McDelicious code is employed for the aforementioned yield estimations, although it is not an open code. Recently, a deuteron-induced reaction library, JENDL/DEU-2020, was released by the Japan Atomic Energy Agency. Thus, employing benchmark tests, such as the Particle and Heavy Ion Transport code System (PHITS) + JENDL/DEU-2020, Monte Carlo N-Particle + JENDL/DEU-2020, and McDelicious, we confirm that PHITS (or Monte Carlo N-Particle (MCNP)) + JENDL/DEU-2020 effectively reproduces the experimental data and McDelicious results. We apply PHITS + JENDL/DEU-2020 to the yield estimations of the neutron, gamma, and charged particles in a Li target and to the yield estimation of the charged particles in the target backplate for A-FNS. The estimated production rates of tritium and 7Be during the continuous operation using a deuteron beam of 40 MeV and 125 mA are 1.4 × 1016 atoms/s (2.3 g/FPY) and 5.9 × 1014 atoms/s (0.21 g/FPY), respectively, and the estimated production rates of He and H in the target backplate for A-FNS are 3.2 × 102 and 1.8 × 103 appm/FPY, respectively.

    DOI: 10.1016/j.fusengdes.2024.114320

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  6. Application of a single crystal CVD diamond detector for fast neutron measurement in high dose and mixed radiation fields Reviewed

    Kobayashi M.I., Yoshihashi S., Ogawa K., Isobe M., Aso T., Hara M., Sangaroon S., Tamaki S., Murata I., Osakabe M.

    Digest of Technical Papers - IEEE International Conference on Consumer Electronics     2024

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:Digest of Technical Papers - IEEE International Conference on Consumer Electronics  

    This paper presents the method to evaluate the fast neutron energy spectrum under mixed radiation field using the single crystal CVD diamond detector. The pulse shape discrimination based on the shape and width of the pulse was applied to extract the event in which fast neutron hits at a specific depth of the single crystal diamond. Unfolding of the measured energy deposition spectrum induced by extracted pulses could deduce the neutron energy spectrum. An experiment using 14.1 MeV mono-energetic neutron source demonstrated the reliable capability of this method to evaluate the neutron energy spectrum quantitatively.

    DOI: 10.1109/ICCE59016.2024.10444274

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

    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

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:Journal of Materials Science: Materials in Electronics  

    The glow curve components and thermoluminescence (TL) parameters of BeO ceramics plates with high bioequivalence were analyzed using extremely slow heating rates. Thermalox 995 was used as the BeO ceramic plates, which is a material with a BeO content of 99.5% or higher. The size of the plates was 10 × 10 × 0.7 mm3 with a density of 2.85 g/cm3, and an effective atomic number of 7.13. A linear accelerator was used for irradiation of the BeO plates at 5 Gy of 6 MV X-rays. After irradiation, the TL glow curve was measured using an in-house developed measurement instrument; the TL intensity was recorded from 50 to 400 °C with heating rates of 0.133, 0.05, and 0.005 °C/s used in three patterns. General-order kinetics were used for the theoretical analysis, which takes recapture into account. After irradiation, post-annealing was performed in the range of 50 to 350 °C at 50 °C intervals, and component analysis of the glow curves was also performed. The TL parameters were calculated from glow curves measured up to a heating rate that was three orders of magnitude slower than that previously measured. The activation energy and frequency factor for the main glow component at low temperatures were 1.15 eV and 1.11 × 1011/s, respectively, while those for the main glow component at high temperatures were 1.74 eV and 8.65 × 1013/s. The glow peak for the BeO ceramic plates were also determined have a low TL intensity component in close proximity to these two glow components. Furthermore, an increase in TL efficiency was observed when the glow curve was measured using an extremely slow heating rate. This may be due to a change of the carriers from TL-inactive when the glow curve is measured with a fast heating rate to TL-active with a longer thermal excitation time.

    DOI: 10.1007/s10854-023-11378-7

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  8. Measurement of 6Li burn-up reaction rate using a single crystal CVD diamond detector under fast neutron irradiation environment Reviewed

    Kobayashi, MI; Yoshihashi, S; Ogawa, K; Isobe, M; Miwa, M; Toyama, S; Matsuyama, S; Osakabe, M

    FUSION ENGINEERING AND DESIGN   Vol. 193   2023.8

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:Fusion Engineering and Design  

    The study aimed to develop a technique for measuring the 6Li burn-up rate using a single crystal diamond (SCD) detector (SDD) made by chemical vapor deposition (CVD) with a thin lithium fluoride foil. The method relied on pulse shape discrimination (PSD) to separate pulses by nuclear reaction products of 6Li from pulses due to fast neutrons and gamma-rays. By applying the PSD method, the rectangular shape pulses induced by events occurred at the specific depth positions of the SCD, i.e., the incident surface, the ballistic center region (BCR), and the rear surface, were extracted. Thereafter, pulses occurred each specific depth position of the SCD were discriminated according to the pulse width. Due to a short range of nuclear reaction products in the SCD, pulses at the incident surface should be induced by both fast neutrons and nuclear reaction products, although pulses at the BCR are caused by fast neutron only. The study demonstrated that quantitative measurements of nuclear reaction products in the 6Li burn-up reaction under fast neutron irradiation can be achieved using only one SDD by analyzing event rates at the incident surface and in the BCR region.

    DOI: 10.1016/j.fusengdes.2023.113799

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

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

    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment   Vol. 1046   2023.1

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    DOI: 10.1016/j.nima.2022.167636

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

    Kaburagi Masaaki, Shimazoe Kenji, Terasaka Yuta, Tomita Hideki, Yoshihashi Sachiko, Yamazaki Atsushi, Uritani Akira, Takahashi Hiroyuki

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

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

    DOI: 10.1016/j.nima.2022.112976

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  11. Measurements of gamma-rays and neutrons in BNCT irradiation field using thermoluminescent phosphor Reviewed

    Shinsho Kiyomitsu, Oh Ryoken, Tanaka Masaya, Sugioka Natsumi, Tanaka Hiroki, Wakabayashi Genichiro, Takata Takushi, Chang Weishan, Matsumoto Shinnosuke, Okada Go, Sugawara Satoru, Sasaki Ema, Watanabe Kenichi, Koba Yusuke, Nagasaka Kosei, Yoshihashi Sachiko, Uritani Akira, Negishi Toru

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

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

    DOI: 10.35848/1347-4065/ac971e

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  12. 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 Shogo, Yoshihashi Sachiko, Hamaji Yukinori, Shen Jingjie, Tsuchida Kazuki, Nishitani Takeo, Kiyanagi Yoshiaki, Tsurita Yukio, Watanabe Kenichi, Yamazaki Atsushi, Uritani Akira

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

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

    DOI: 10.1016/j.nima.2022.167414

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

    Masaya Tanaka, Ryoken Oh, Natsumi Sugioka, Hiroki Tanaka, Takushi Takata, Genichiro Wakabayashi, Satoru Sugawara, Kenichi Watanabe, Akira Uritani, Sachiko Yoshihashi, Kosei Nagasaka, Go Okada, Toru Negishi, Kiyomitsu Shinsho

    Journal of Materials Science: Materials in Electronics   Vol. 33 ( 25 ) page: 20271 - 20279   2022.9

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

    In boron neutron capture therapy (BNCT), neutrons and γ-rays cause different biological effects, and it is necessary to discriminate between them for treatment planning and periodic inspections. Currently, the BeO powder thermoluminescence dosimeter (BeO powder TLD) is used for γ-ray dosimetry in mixed neutron and γ-ray fields due to the small capture cross section for neutrons, but correction is required because of the effects of neutron-induced activation. Besides, sales of BeO powder TLDs have been discontinued because the highly toxic BeO is readily dispersed when the detector is damaged. Therefore, the development of alternative replacement technologies for BeO powder TLDs that are not affected by neutrons is an important issue. In this study, we investigated the measurement of the γ-ray dose during BNCT using a BeO ceramic TLD, whereby the BeO was not released into the air. After 5, 15, 30, and 60 min of irradiation using the Kyoto University Research Reactor, the amount of thermoluminescence (TL) from the BeO ceramic TLD was shown to increase with irradiation time. In addition, the γ-ray dose, which was derived by converting the amount of TL to the dose, showed excellent proportionality to the irradiation time and was found to be comparable to the γ-ray dose measured with a BeO powder TLD. These results demonstrated that the BeO ceramic TLD can selectively measure only the γ-ray dose without influence by neutrons. Thus, our approach represents a new γ-ray dose measurement strategy that does not require correction for the contribution from thermal neutrons.

    DOI: 10.1007/s10854-022-08843-0

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  14. 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

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    DOI: 10.3390/jne3030012

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  15. Evaluation of Induced Radioactivity Generated during LHD Deuterium Plasma Experiments

    YOSHIHASHI Sachiko, YAMADA Hayato, KOBAYASHI Makoto, NISHITANI Takeo, YAMAZAKI Atsushi, ISOBE Mitsutaka, OGAWA Kunihiro, URITANI Akira

    Plasma and Fusion Research   Vol. 17 ( 0 ) page: 2405096 - 2405096   2022.8

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:The Japan Society of Plasma Science and Nuclear Fusion Research  

    <p>Neutrons are generated in a fusion plasma and induce various radionuclides via a nuclear reaction with fusion reactor materials. Evaluating the kinds of nuclide and the amount of induced radioactivity is important for decommissioning planning and regular maintenance. In this study, we verified a long-term prediction model of induced radioactivity in the large helical device (LHD) model by comparing induced radioactivity generated during deuterium plasma experiments in LHD with results calculated using a high-energy particle-induced radioactivity code. The metals employed for activation were SUS316L, Co, Mo, and Ni. During the deuterium plasma experiments, these materials were placed on an 8-O port of the LHD, and the induced radioactivity was measured weekly. To computed induced radioactivity using DCHAIN-SP, the neutron energy spectrum was computed using the LHD model with the Monte-Carlo simulation code PHITS. Although the calculated and measured radioactivity of <sup>58</sup>Co and <sup>54</sup>Mo agreed well, the calculated values of <sup>60</sup>Co and <sup>99</sup>Mo were underestimated. However,low-energy components could be improved by incorporating peripheral devices into the LHD model, resulting in more accurate radioactivity predictions.</p>

    DOI: 10.1585/pfr.17.2405096

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

    Ishikawa Akihisa, Watanabe Kenichi, Yoshihashi Sachiko, Sakurai Yoshinori, Kumada Hiroaki, Tanaka Hiroki, Uritani Akira, Kiyanagi Yoshiaki

    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 Makoto I., YOSHIHASHI Sachiko, YAMANISHI Hirokuni, SANGAROON Siriyaporn, OGAWA Kunihiro, ISOBE Mitsutaka, URITANI Akira, OSAKABE Masaki

    Plasma and Fusion Research   Vol. 17 ( 0 ) page: 2405045 - 2405045   2022.6

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:The Japan Society of Plasma Science and Nuclear Fusion Research  

    <p>Thermal neutron flux evaluation using a single crystal diamond detector (SDD) was carried out in the core region of the UTR-KINKI reactor where a mixed radiation field by thermal and fast neutrons and gamma-ray exists. The pulse shape discrimination method to extract pulses with a rectangular shape as well as a wide pulse-width was established to exclude pulses induced by gamma-rays. The SDD, using a <sup>6</sup>LiF thermal neutron converter, is able to detect pulse events caused not only by fast neutrons but also by thermal neutrons through energy depositions into the diamond by energetic alpha and triton particles induced by thermal neutrons. Additionally, the SDD without the thermal neutron converter was used for the measurement of the energy deposition events only by fast neutrons. A comparison of the pulse counts of the SDD with or without the thermal neutron convertor deduced the energy deposition spectra by thermal neutrons. The thermal neutron flux in the core region of the UTR-KINKI reactor was evaluated to be 7.6×10<sup>6 </sup>n cm<sup>−2 </sup>s<sup>−1 </sup>W<sup>−1 </sup>up to a reactor power of 1 W.</p>

    DOI: 10.1585/pfr.17.2405045

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  18. A comprehensive evaluation of the thermal neutron detection efficiency by a single crystal CVD diamond detector with a LiF thermal neutron converter

    Kobayashi Makoto I, Yoshihashi Sachiko, Ogawa Kunihiro, Isobe Mitsutaka, Sangaroon Siriyaporn, Kamio Shuji, Fujiwara Yutaka, Osakabe Masaki

    FUSION ENGINEERING AND DESIGN   Vol. 179   2022.6

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

    DOI: 10.1016/j.fusengdes.2022.113117

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

    Nishitani Takeo, Tanagami Yuuki, Yoshihashi Sachiko, Tsuchida Kazuki, Yamazaki Atsushi, Uritani Akira

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

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

    DOI: 10.1080/00223131.2021.1996297

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

    Takeo Nishitani, Sachiko Yoshihashi, Kunihiro Ogawa, Misako Miwa, Shigeo Matsuyama, Akira Uritani

    Journal of Nuclear Science and Technology   Vol. 59 ( 4 ) page: 534 - 541   2022.4

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    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:Informa UK Limited  

    DOI: 10.1080/00223131.2021.1981475

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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

    Akihisa Ishikawa, Kenichi Watanabe, Atsushi Yamazaki, Sachiko Yoshihashi, Shigefumi Imai, Akihiko Masuda, Tetsuro Matsumoto, Hiroki Tanaka, Yoshinori Sakurai, Mitsuhiro Nogami, Keitaro Hitomi, Akira Uritani, Hideki Harano

    Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment   Vol. 1025   2022.2

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

    An optical fiber-based neutron detector can be used as a real-time neutron monitor for an intense neutron field. In this study, optical fiber-based neutron detectors were fabricated using Li-glass scintillator. The thermal neutron sensitivity, upper limit of the output linearity, and response to gamma rays from 60Co and Cd were evaluated. The thermal neutron sensitivity was proportional to the mass of the Li-glass scintillator, and the calibration factor was 2.06 × 10−6 and 3.18 × 10−6 cps/(n/cm 2/s)/μg for the lower-level discrimination of the peak and valley channel, respectively. The detector output linearity was confirmed to be up to nearly 2 Mcps. While evaluating the response to gamma rays, for both 60Co and Cd, the gamma-ray counting rate was found to be smaller than the uncertainty associated with counting statistics in most expected applications where the neutron counting rate was >1 kcps.

    DOI: 10.1016/j.nima.2021.166074

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

    NISHITANI Takeo, YOSHIHASHI Sachiko, KUMAGAI Kohki, KONDO Keitaro, URITANI Akira

    Plasma and Fusion Research   Vol. 16 ( 0 ) page: 1405104 - 1405104   2021.11

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    Language:English   Publishing type:Research paper (scientific journal)   Publisher:The Japan Society of Plasma Science and Nuclear Fusion Research  

    <p>An accelerator-based neutron source using d-Li reactions is one of the most promising neutron sources for fusion material irradiation facilities such as IFMIF, where 40 MeV deuterons bombard a liquid lithium target. The neutron yield estimation including angular neutron spectra is one of the most important issues in the design of such irradiation facilities. Recently, JAEA released deuteron nuclear data of JENDL/DEU-2020 in ACE format file for Monte Carlo codes such as MCNP, and in Frag-Data format for the PHITS code. We carry out the benchmark calculations of d-Li neutron yield by using PHITS with Frag-Data, MCNP with JENDL/DEU-2020, and MCNP/PHITS with built-in nuclear reaction models. Those calculation results are compared with experimental data. It is confirmed that PHITS with Frag Data and MCNP with JENDL/DEU-2020 reproduce well the experimental data. Those are useful for the neutron yield estimation and also the irradiation field characterization of IFMIF and similar facilities.</p>

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  23. Gamma-ray Dosimetry in the BNCT Irradiation Field Using BeO Optically Stimulated Luminescence Dosimeter

    Watanabe Kenichi, Nakamura Satoru, Nagasaka Kosei, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2021.1 ( 0 ) page: 576 - 576   2021.2

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    DOI: 10.11470/jsapmeeting.2021.1.0_576

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  24. Gamma-ray Dosimetry in the BNCT Irradiation Field Using BeO Optically Stimulated Luminescence Dosimeter

    Watanabe Kenichi, Nakamura Satoru, Nagasaka Kosei, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2021.1 ( 0 ) page: 576 - 576   2021.2

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    DOI: 10.11470/jsapmeeting.2021.1.0_576

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

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

    Applied Radiation and Isotopes   Vol. 168   page: 109553   2021.2

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    As the commissioning phase of the Nagoya University Accelerator-driven Neutron Source for boron neutron capture therapy, in-phantom thermal neutron flux measurements were conducted using a small ^<6>LiF/Eu:CaF_2 scintillator detector and activation foils. The spatial distribution of the measured thermal neutron flux agreed with the Monte Carlo simulation results. Based on this comparison, the free-in-air neutron spectrum, calculated at the exit aperture, was verified and the epithermal neutron flux, at a 0.25 mA proton current, was evaluated as (1.49±0.10)×10^<7> n/(c㎡ s).

    DOI: 10.1016/j.apradiso.2020.109553

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

    Kobayashi M.I

    Fusion Engineering and Design   Vol. 161   2020.12

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    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 reaction 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

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  27. In Vitro Studies to Define the Cell-Surface and Intracellular Targets of Polyarginine-Conjugated Sodium Borocaptate as a Potential Delivery Agent for Boron Neutron Capture Therapy

    Atsushi Fujimura, Seiji Yasui, Kazuyo Igawa, Ai Ueda, Kaori Watanabe, Tadashi Hanafusa, Yasuaki Ichikawa, Sachiko Yoshihashi, Kazuki Tsuchida, Atsunori Kamiya, Shuichi Furuya

    CELLS   Vol. 9 ( 10 )   2020.10

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    Boron neutron capture therapy (BNCT) requires pharmaceutical innovations and molecular-based evidence of effectiveness to become a standard cancer therapeutic in the future. Recently, in Japan, 4-borono-L-phenylalanine (BPA) was approved as a boron agent for BNCT against head and neck (H&N) cancers. H&N cancer appears to be a suitable target for BPA-BNCT, because the expression levels of L-type amino acid transporter 1 (LAT1), one of the amino acid transporters responsible for BPA uptake, are elevated in most cases of H&N cancer. However, in other types of cancer including malignant brain tumors, LAT1 is not always highly expressed. To expand the possibility of BNCT for these cases, we previously developed poly-arginine peptide (polyR)-conjugated mercaptoundecahydrododecaborate (BSH). PolyR confers the cell membrane permeability and tumor selectivity of BSH. However, the molecular determinants for the properties are not fully understood. In this present study, we have identified the cluster of differentiation 44 (CD44) protein and translational machinery proteins as a major cell surface target and intracellular targets of BSH-polyR, respectively. CD44, also known as a stem cell-associated maker in various types of cancer, is required for the cellular uptake of polyR-conjugated molecules. We showed that BSH-polyR was predominantly delivered to a CD44(High) cell population of cancer cells. Once delivered, BSH-polyR interacted with the translational machinery components, including the initiation factors, termination factors, and poly(A)-biding protein (PABP). As a proof of principle, we performed BSH-polyR-based BNCT against glioma stem-like cells and revealed that BSH-polyR successfully induced BNCT-dependent cell death specifically in CD44(High) cells. Bioinformatics analysis indicated that BSH-polyR would be suitable for certain types of malignant tumors. Our results shed light on the biochemical properties of BSH-polyR, which may further contribute to the therapeutic optimization of BSH-BNCT in the future.

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

    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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    Neutron emission anisotropy caused by neutral beam injection was observed by the neutron activation measurement in deuterium plasmas confined in the Large Helical Device. The shot-integrated fast neutron flux was measured by the irradiation of activation foils at two irradiation ends located at different ports. The ratio of the flux at the outside horizontal port to that at the lower port was used as an index of neutron emission anisotropy. The dependence of the ratio on the direction of the neutral beam injection was confirmed by comparing cases of tangential, perpendicular and both tangential and perpendicular neutral beam injections. Neutron emission anisotropy was numerically evaluated assuming these three cases of neutral beam injection. The analysis of neutron emission anisotropy comprises the evaluation of the velocity distribution function of energetic deuterons following guiding-centre orbits, calculation of the double-differential emission spectrum of neutrons produced by the D(d,n) 3&rm He reaction and neutron transport calculation. The obtained numerical results are qualitatively consistent in the dependence of neutron emission anisotropy on the neutral-beam-injection direction with the observed experimental data.

    DOI: 10.1088/1741-4326/ab90c9

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

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

    RADIATION MEASUREMENTS   Vol. 133   2020.4

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    BNCT is a radiation therapy using neutrons. For dosimetry in BNCT, it is important to evaluate the thermal neutron distribution in a water phantom irradiated with neutrons used in the therapy. We proposed application of a small 6Li-based scintillator neutron detector with an optical fiber into a comparison study between simulation and experimental results in BNCT. In this paper, we compared simulation and experimental results for depth profile of 6Li(n,α) reaction rate in a water phantom of BNCT using a developed small 6Li-based scintillator neutron detector. The experimental results well agreed with the simulation ones. However, we found that the self-shielding effect in the detector will be significant even for a small LiF/Eu:CaF2 eutectics scintillator having the mass of 100 μg. We concluded that we have to consider the self-shielding effect in the small 6Li-based scintillator neutron detector when comparing simulation and experimental results of the 6Li(n,α) reaction rate in a water phantom.

    DOI: 10.1016/j.radmeas.2020.106270

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  30. Output linearity and radiation resistance of an optical fiber-based neutron detector using Li-glass scintillator

    Ishikawa Akihisa, Yamazaki Atsushi, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2020.1 ( 0 ) page: 555 - 555   2020.2

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    DOI: 10.11470/jsapmeeting.2020.1.0_555

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  31. Output linearity and radiation resistance of an optical fiber-based neutron detector using Li-glass scintillator

    Ishikawa Akihisa, Yamazaki Atsushi, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2021.1 ( 0 ) page: 555 - 55   2020.2

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    DOI: 10.11470/jsapmeeting.2020.1.0_555

  32. Basic study on a LiF-Eu:CaF<inf>2</inf> mixed powder neutron scintillator

    Watanabe K

    Nuclear Instruments and 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

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  33. Sensitivity and linearity of optical fiber-based neutron detectors using small<sup>6</sup>Li-based scintillators

    Ishikawa A

    Nuclear Instruments and 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.2018.11.120

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  34. Numerical Study of Turbulent Heat transfer enhancement in square-duct flow through of inline V-shaped discrete ribs

    Yu Stu. S, Tsuneyoshi T, Hamaji Y, Yoshihashi S, Ito T, Tsuji Y

    The Proceedings of Conference of Tokai Branch   Vol. 2020.69 ( 0 ) page: 520   2020

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    DOI: 10.1299/jsmetokai.2020.69.520

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  35. Design of Neutron Spectrum-Shaping Assembly Around the Pneumatic Tube-End in the LHD Torus Hall for the Medical Research Application

    KOBAYASHI Makoto I., OGAWA Kunihiro, ISOBE Mitsutaka, NISHITANI Takeo, NISHIMURA Teruki, MUKAI Keisuke, YOSHIHASHI Sachiko, OSAKABE Masaki

    Plasma and Fusion Research   Vol. 15 ( 0 ) page: 2405043 - 2405043   2020

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    <p>The designs of neutron spectrum-shaping assembly (NSSA) composed with various shielding materials with natural isotopic abundance were evaluated to construct the neutron field dominated with thermal neutron or epi-thermal neutron for the application of neutron filed in the torus hall of LHD toward the BNCT research. According to the neutron transport calculation by MCNP6, the fast neutron moderation efficiency was higher in polyethylene (PE) compared to lithium fluoride (LiF) and magnesium fluoride (MF), although LiF showed relatively large epi-thermal and thermal neutron absorption. This comparison showed that the thermal neutron field can be effectively achieved with using PE. For constructing the NSSA which can provide the neutron field dominated with epi-thermal neutron, several NSSA designs were evaluated with respect to fast neutron flux, epi-thermal neutron flux, and gamma-ray dose. The combination of MF, lead (Pb) and cadmium (Cd) can provide the good epi-thermal neutron field with the mitigations of fast neutron flux and gamma-ray dose, which is also suitable for BNCT research in the torus hall of LHD.</p>

    DOI: 10.1585/pfr.15.2405043

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  36. 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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    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 have been 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 the limiting factors for the dynamic range of optical-fiber-based neutron detectors. In this work, we applied a small Li glass scintillator to a quartz optical-fiber-based neutron detector using an optical fiber with high numerical aperture 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: 10.18494/SAM.2020.2748

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  37. Crystal quality evaluation of TlBr by wavelength-resolved neutron imaging

    Watanabe Kenichi, Matsumoto Kio, Hitomi Keitaro, Nogami Mitsuhiro, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.2 ( 0 ) page: 519 - 519   2019.9

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    DOI: 10.11470/jsapmeeting.2019.2.0_519

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  38. Crystal quality evaluation of TlBr by wavelength-resolved neutron imaging

    Watanabe Kenichi, Matsumoto Kio, Hitomi Keitaro, Nogami Mitsuhiro, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.2 ( 0 ) page: 519 - 519   2019.9

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    DOI: 10.11470/jsapmeeting.2019.2.0_519

  39. 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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    A single crystal CVD diamond detector (SDD) was installed in the torus hall of the Large Helical Device (LHD) to measure neutron during deuterium plasma operation. The LiF foil with 95.62% of 6Li isotope enrichment pasted on the detector was used as the thermal neutron convertor. The energetic ions of 2.0 MeV alpha and 2.7 MeV triton particles generated by the nuclear reaction of neutron with 6Li in LiF foil. Then, energetic ions deposited the energy into diamond, producing a signals in 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 charge in SDD during one plasma shot in LHD was linearly propotional to the neutron yield 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.

    DOI: 10.1088/1748-0221/14/09/C09039

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

    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 ( 06 ) page: T06010 - T06010   2019.6

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

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  41. Improvement of the single edge fitting mode in the Bragg edge analysis code RITS

    Ohmae Kazuma, Watanabe Kenichi, Uritani Akira, Yamazaki Atsushi, Yoshihashi Sachiko, Kiyanagi Yoshiaki, Sato Hirotaka

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.1 ( 0 ) page: 561 - 561   2019.2

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    DOI: 10.11470/jsapmeeting.2019.1.0_561

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  42. Measurement of BNCT Neutron Field Using Optical Fiber-Based Neutron Detector

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

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.1 ( 0 ) page: 526 - 526   2019.2

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    DOI: 10.11470/jsapmeeting.2019.1.0_526

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

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

    Progress in Nuclear Science and Technology   Vol. 6 ( 0 ) page: 122 - 125   2019.1

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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

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  44. 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

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

    Progress in Nuclear Science and Technology   Vol. 6 ( 0 ) page: 238 - 242   2019.1

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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

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  45. Evaluation of imaging plate measurement for activated indium as fast-neutron detector in large radiation field

    Kobayashi Makoto, Nishitani Takeo, Kato Akemi, Saze Takuya, Tanaka Tomoyo, Yoshihashi Sachiko, Ogawa Kunihiro, Isobe Mitsutaka

    Progress in Nuclear Science and Technology   Vol. 6 ( 0 ) page: 58 - 62   2019.1

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    The application of imaging plate (IP) method using indium foils to measure the distribution of fast neutron in large area was evaluated in this work. The radioactive nuclides of indium were individually quantified by high-purity germanium detector (HPGe) and chronological IP measurements. The detection efficiencies of each radioactive nuclide for various thicknesses of foil mylar polyester film were summarized. The scope of application for proposed method were clearly dependent on the flux ratio of fast and thermal neutron, limiting the applicable region only being close to the neutron source.

    DOI: 10.15669/pnst.6.58

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

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

    Plasma and Fusion Research   Vol. 14 ( 0 ) page: 3405162 - 3405162   2019

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    <p>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) <sup>3</sup>He 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.</p>

    DOI: 10.1585/pfr.14.3405162

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  47. Numerical heat transfer study of turbulent square-duct flow through inline V-shaped discrete ribs

    Yu Stu. Shichao, Tsuneyoshi Tatsuya, Yoshihashi Sachiko, Hamaji Yukinori, Ito Takahiro, Tsuji Yoshiyuki

    The Proceedings of the Fluids engineering conference   Vol. 2019 ( 0 ) page: OS8-07 - 7   2019

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    <p>A numerical study has been conducted to examine turbulent flow and heat transfer characteristics in a three-dimensional square-duct with V-shaped ribs. The computations are based on RANS and LES models. Water is the working fluid with the flow rate of which Reynolds numbers equals to 18500. The computation reveals that two symmetrical fully developed helical flow and developed heat transfer profile are generated. Effects of different rib shape on thermal characteristics for a ribbed duct flow are investigated. The change of the shape leads to increase in heat transfer and pressure loss. The velocity profile in the vicinity of ribs and streamline has been investigated, indicates that the different flow structures generated by the rib shape leads to superior heat transfer performance. Vortices are visualized, which indicates the connection between the heat transfer and flow structure</p>

    DOI: 10.1299/jsmefed.2019.os8-07

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  48. First measurements of thermal neutron distribution in the LHD torus hall generated by deuterium experiments

    Kobayashi Makoto, Tanaka Tomoyo, Nishitani Takeo, Ogawa Kunihiro, Isobe Mitsutaka, Kato Akemi, Saze Takuya, Yoshihashi Sachiko, Osakabe Masaki

    FUSION ENGINEERING AND DESIGN   Vol. 137   page: 191 - 195   2018.12

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    For the estimation of the neutron field generated by deuterium plasma operation in the Large Helical Device (LHD), the first measurement of the thermal neutron distribution on the floor level of the LHD torus hall was carried out. For the thermal neutron detection, indium was used as activation foils. The radioactivity of these foils were evaluated by a high-purity germanium detector (HPGe) and an imaging plate (IP). The major components of radioactive isotope of indium was 116mIn. The mapping of thermal neutron distribution in the torus hall was performed. The interactions between neutron and components around LHD were observed in the thermal neutron distribution. Also, the borated polyethylene blocks effectively absorbed the thermal neutron. The thermal neutron distribution evaluated in this work can be helpful to predict the amount of radioactive waste in the torus hall proceeding with deuterium experiment in LHD.

    DOI: 10.1016/j.fusengdes.2018.09.013

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

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

    Proceedings of the International Conference on Neutron Optics (NOP2017)     2018.11

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    DOI: 10.7566/jpscp.22.011003

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  50. Calibration experiment and the neutronics analyses on the LHD neutron flux monitors for the deuterium plasma experiment

    Nishitani Takeo, Ogawa Kunihiro, Isobe Mitsutaka, Kawase Hiroki, Pu Neng, Kashchuk Yuri, Krasilnikov Vitaly, Jo Jungmin, Cheon Munseong, Tanaka Tomoyo, Yoshihashi Sachiko, Li Siyuan, Osakabe Masaki

    FUSION ENGINEERING AND DESIGN   Vol. 136   page: 210 - 214   2018.11

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    Prior to the deuterium experiments of the Large Helical Device (LHD), an in situ neutron calibration experiment was carried out by using an 800 MBq 252Cf neutron source in November 2016, where a neutron flux monitor, a neutron activation system and a vertical neutron camera are calibrated. This paper concentrates on the in situ calibration for the neutron flux monitor. The neutron flux monitor based on 235U fission chambers and 10B and 3He proportional counters are positioned at three locations outside the LHD cryostat. The counts are measured during continuous rotation of the 252Cf neutron source on the typical magnetic axis of the plasma by a toy train, where the neutron source can be regarded as a ring neutron source. Detection efficiencies for the 252Cf ring source are derived by (total counts)/(total emitted neutron number) in the continuous rotation of the neutron source. Detection efficiencies for the real plasma neutron source are obtained from the measured detection efficiencies with the correction factor taking account of the deference between the 252Cf ring source and the real plasma neutron source evaluated by MCNP calculations with the three-dimensional model of the LHD. Finally, the uncertainty of the total neutron emission rate measurement is discussed.

    DOI: 10.1016/j.fusengdes.2018.01.053

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  51. Neutron Diagnostics in the Large Helical Device

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

    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 $3.3 \times 10^{15}$ (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

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  52. What’s diversity for?

    Yoshida Hiroko, Yoshihashi Sachiko

    Journal of the Atomic Energy Society of Japan   Vol. 60 ( 5 ) page: 303 - 306   2018

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    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:Atomic Energy Society of Japan  

    DOI: 10.3327/jaesjb.60.5_303

    CiNii Research

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

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

    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 foils stacked with total mass of approximately 18 g were prepared. Each capsule was irradiated over 15 h 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 from three-dimensional neutron transport calculations using the Monte Carlo neutron transport simulation code 6. The activation response coefficients of 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 with results from three-dimensional neutron calculations using the Monte Carlo neutron transport simulation code 6.

    DOI: 10.1063/1.5009475

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    CiNii Research

  54. Measurement of transient flow characteristics of target flow in water experiment for IFMIF

    Matsuda Shotaro, Kanemura Takuji, Kondo Hiroo, Kaji Sayaka, Okita Takafumi, Yoshihashi Sachiko, Hoashi Eiji, Horiike Hiroshi

    FUSION ENGINEERING AND DESIGN   Vol. 124   page: 1096 - 1100   2017.11

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    DOI: 10.1016/j.fusengdes.2017.03.111

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  55. Study of the correction method for quenching effects of a small size dosimeter using an optical fiber and optically stimulated luminescence

    Hirata Yuho, Yamazaki Atsushi, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira, Koba Yusuke, Matsufuji Naruhiro, Toshito Toshiyuki, Yanagida Takayuki

    JSAP Annual Meetings Extended Abstracts   Vol. 2017.2 ( 0 ) page: 453 - 453   2017.8

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    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:The Japan Society of Applied Physics  

    DOI: 10.11470/jsapmeeting.2017.2.0_453

    CiNii Research

  56. 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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    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:MYU, SCIENTIFIC PUBLISHING DIVISION  

    To monitor an actual dose in a patient's body during radiotherapy treatment, we have developed a small-size dosimeter of an optical fiber probe mounting optically stimulated luminescence (OSL) materials at the tip. The OSL materials show a quenching effect when they are irradiated by charged particles with high linear energy transfer (LET). We evaluate the particle dependence on the quenching effect in the small-size OSL dosimeter probe. Eu:BaFBr and Ce:CaF2 were adopted as OSL materials, and two types of small-size dosimeter were fabricated. We irradiated 290 MeV/u carbon ions, 150 MeV/u helium ions, and 225 MeV protons and measured the Bragg peak. The Eu:BaFBr small-size dosimeter showed the quenching effect in these three types of particle irradiation. The Ce:CaF2 small-size dosimeter showed the quenching effect only in carbon ion irradiation. The luminescence efficiencies of Eu:BaFBr were compared among these three charged particles. The quenching effect of Eu:BaFBr is independent of the irradiated particles.

    DOI: 10.18494/SAM.2017.1626

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  57. The design of the beam line of the Nagoya University accelerator-driven neutron source

    Ito I., Furusawa D., Hirota K., Ichikawa G., Iwashita Y., Kitaguchi M., Kiyanagi Y., Menjo Y., Miwata Y., Shimizu H.M., Tsuchida K., Tsuchikawa Y., Tsurita Y., Uritani A., Watanabe K., Yamagata Y., Yamazaki A., Yoshihashi S.

    Proceedings of Science   Vol. 2017-January   2017

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    The Nagoya University Accelerator driven Neutron Source (NUANS) are now constructing at main campus of Nagoya University. The electrostatic accelerator is used with the maximum proton energy and power of 2.8MeV, 15mA(42kW) respectively. Two neutron beam lines are planned at NUANS. The first beam line is dedicated to BNCT. The second beam line is designed for research and development of neutron devices and neutron imaging. The neutrons used for the 2nd beam line are generated by using the (p, n) reaction of beryllium. We designed a compact target station for the 2nd beam line with the dimension of 90cm×90cm×95cm by using radiation shielding simulation. We considered neutron beam extraction with the cross section of 10cm×10cm for radiography at the 2nd beam line. The neutron flux is expected to be about 104n cm-2s-1 with the energy less than 0.1 eV at the position of 2m from the neutron source. We also calculated the proton beam transport from the exit of the accelerator to the neutron production target of the 2nd beam line.

    Scopus

  58. The design of the beam line of the Nagoya University accelerator-driven neutron source

    Ito I, Furusawa D, Hirota K, Ichikawa G, Iwashita Y, Kitaguchi M, Kiyanagi Y, Menjo Y, Miwata Y, Shimizu H.M, Tsuchida K, Tsuchikawa Y, Tsurita Y, Uritani A, Watanabe K, Yamagata Y, Yamazaki A, Yoshihashi S

    Proceedings of Science   Vol. 2017-January   2017

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    Language:Japanese   Publishing type:Research paper (scientific journal)   Publisher:Proceedings of Science  

    The Nagoya University Accelerator driven Neutron Source (NUANS) are now constructing at main campus of Nagoya University. The electrostatic accelerator is used with the maximum proton energy and power of 2.8MeV, 15mA(42kW) respectively. Two neutron beam lines are planned at NUANS. The first beam line is dedicated to BNCT. The second beam line is designed for research and development of neutron devices and neutron imaging. The neutrons used for the 2nd beam line are generated by using the (p, n) reaction of beryllium. We designed a compact target station for the 2nd beam line with the dimension of 90cm×90cm×95cm by using radiation shielding simulation. We considered neutron beam extraction with the cross section of 10cm×10cm for radiography at the 2nd beam line. The neutron flux is expected to be about 104n cm-2s-1 with the energy less than 0.1 eV at the position of 2m from the neutron source. We also calculated the proton beam transport from the exit of the accelerator to the neutron production target of the 2nd beam line.

  59. Engineering validation for lithium target facility of the IFMIF under IFMIF/EVEDA project

    Wakai E, Kanemura T, Kondo H, Hirakawa Y, Ito Y, Serizawa H, Kawahito Y, Higashi T, Suzuki A, Fukada S, Furuya K, Esaki K, Yagi J, Tsuji Y, Ito T, Niitsuma S, Yoshihashi-Suzuki S, Watanabe K, Furukawa T, Groeschel F, Micciche G, Manorri S, Favuzza P, Nitti F. S, Heidinger R, Terai T, Horiike H, Sugimoto M, Ohira S, Knaster J

    NUCLEAR MATERIALS AND ENERGY   Vol. 9   page: 278 - 285   2016.12

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    DOI: 10.1016/j.nme.2016.05.012

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  60. Free-Surface Characteristics of a Liquid Li Wall Jet

    Kanemura Takuji, Kondo Hiroo, Sugiura Hirokazu, Yoshihashi Sachiko, Hoashi Eiji, Muroga Takeo, Furukawa Tomohiro, Hirakawa Yasushi, Wakai Eiichi, Horiike Hiroshi

    PLASMA AND FUSION RESEARCH   Vol. 11   2016.10

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    DOI: 10.1585/pfr.11.1405117

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  61. Laser reflection measurement on liquid lithium slow surface flow Reviewed

    Sachiko Yoshihashi, Tsubasa Masaoka, Eiji Hoashi, Takafumi Okita, Hiroo Kondo, Takuji Kanemura, Nobuo Yamaoka, Hiroshi Horiike

    Fusion Engineering and Design   Vol. 102   page: 108   2016.1

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  62. Mock-up experiment at Birmingham University for BNCT project of Osaka University - Neutron flux measurement with gold foil

    S. Tamaki, M. Sakai, S. Yoshihashi, M. Manabe, N. Zushi, I. Murata, E. Hoashi, I. Kato, S. Kuri, S. Oshiro, M. Nagasaki, H. Horiike

    Applied Radiation and Isotopes   Vol. 106   page: 72 - 4   2015.12

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    Mock-up experiment for development of accelerator based neutron source for Osaka University BNCT project was carried out at Birmingham University, UK. In this paper, spatial distribution of neutron flux intensity was evaluated by foil activation method. Validity of the design code system was confirmed by comparing measured gold foil activities with calculations. As a result, it was found that the epi-thermal neutron beam was well collimated by our neutron moderator assembly. Also, the design accuracy was evaluated to have less than 20% error.

    DOI: 10.1016/j.apradiso.2015.07.037

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    PubMed

  63. Liquid Li based neutron source for BNCT and science application.

    Horiike H, Murata I, Iida T, Yoshihashi S, Hoashi E, Kato I, Hashimoto N, Kuri S, Oshiro S

    Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine   Vol. 106   page: 92 - 4   2015.12

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    DOI: 10.1016/j.apradiso.2015.07.026

    PubMed

  64. Measurement of Li target thickness in the EVEDA Li Test Loop Reviewed

    Takuji Kanemura, Hiroo Kondo, Tomohiro Furukawa, Yasushi, Hirakawa, Eiji Hoashi, Sachiko Yoshihashi, Hiroshi Horiike, Eiichi Wakai

    Fusion Engineering and Design   Vol. 98-99   page: 2638   2015.10

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  65. Certification of contact probe measurement of surface wave of Li jet for IFMIF Reviewed

    Takafumi Okita, Eiji Hoashi, Sachiko Yoshihashi, Hiroo Kondo, Takuji Kanemura, Nobuo Yamaoka, Hiroshi Horiike

    Fusion Engineering and Design   Vol. 98-99   page: 2050   2015.10

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  66. Optical measurement of the amount of evaporation of liquid metal lithium Reviewed

    Sachiko Yoshihashi, Noriyuki Teranishi, Kohei Yamamoto, Daisuke Izawa, Takafumi Okita, Eiji Hoashi, Hiroshi Horiike

    Journal of Radioanalytical and Nuclear Chemistry   Vol. 305 ( 3 ) page: 953   2015.7

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  67. Evaluation of applicability of laser-based distance meter to measure Li-jet Thickness for IFMIF project, Fusion Engineering and Design Reviewed

    Takuji Kanemura, Hiroo Kondo, Eiji Hoashi, Sachiko Yoshihashi-Suzuki, Nobuo Yamaoka, Hiroshi Horiike, Tomohiro Furukawa, Yasushi Hirakawam Eiich Wakai

    Fusion Engineering and Design   Vol. 89   page: 1647   2014.10

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  68. Metallurgical analysis of lithium test assembly operated for 1200 h Reviewed

    Tomohiro Furukawa, Hiroo Kondo, Takuji Kanemura, Yasushi Hirakawa, Nobuo Yamaoka, Eiji Hoashi, Sachiko Suzuki-Yoshihashi

    Fusion Engineering and Design   Vol. 89   page: 1674   2014.10

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  69. Numerical study on free surface flow on liquid metal lithium for IFMIF Reviewed

    Eiji Hoashi, Sachiko Yoshihashi-Suzuki, Hiroshi namba, Takuji Kanemura, Hiroo Kondo, Tomohiro Furukawa, Nobuo Yamaoka, Hiroshi Horiike

    Fusion Engineering and Design   Vol. 88   page: 2515   2013.10

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  70. Fablrication and performance test of contact-type liquid level sensor for measuring thickness variation of liquid lithium jet in the IFMIF/EVEDA lithium test loop Reviewed

    Takuji Kanemura, Hiroo Kondo, Eiji Hoashi, Sachiko Yoshihashi-Suzuki, Nobuo Yamaoka, Hiroshi Horiike, Tomohiro Furukawa, Yasushi Hirakawa, Mizuho Ida, Izuru Matushita, Eiichi Wakai

    Fusion Engineering and Design   Vol. 88   page: 2547   2013.10

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  71. Characteristics of Surface Oscillation on High Speed Liquid Li Jet Reviewed

    Sachiko Yoshihashi-Suzuki, Eiji Hoashi, Takuji Kanemura, Hiroo Kondo, Nobuo Yamaoka, Hiroshi Horiike

    Fusion Engineering and Design   Vol. 87   page: 1434   2012.10

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  72. Engineering design of contact-type liquid level sensor for measureing thickness vatiation of liqud lithium jet in IFMIF/EVEDA lithium test loop Reviewed

    Takuji Kanemura, Hiroo Kondo, Sachiko Yoshihashi-Suzuki, Eiji Hoashi, Nobuo Yamaoka, Hiroshi Horiike, Tomohiro Furukawa, Mizuho Ida, Kazuyuki Nakamura, Izuru Matsushita, Eiichi Wakai

    Fusion science and technology   Vol. 62   page: 258   2012.7

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  73. Overview: Free surface measurement with renewed nozzle of Osaka Li loop Reviewed

    Sachiko Yoshihashi-Suzuki, Hirokazu Sugiura, Eiji Hoashi, Hiroo Kondo, Takuji Kanemura, Nobuo, Yamaoka, Mizuho Ida, Hiroo Nakamura, Kazuyuki Nakamura, Izuru matsushita, Hiroshi Horiike

    Fusion Engineering and Design   Vol. 86   page: 2635   2011.10

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  74. Surface wave growth characteristics of the high speed liquid Li flow Invited Reviewed

    H. Sugiura, S. Yoshihashi-Suzuki, E. Hoashi, H. Kondo, T. Kanemura, N. Yamaoka, M. Ida, H. Horiike

    Fusion Engineering and Design   Vol. 86   page: 2635 - 2638   2011

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  75. Wave Period of Free-Surface Waves on High-Speed Liquid Lithium Jet for IFMIF Target Invited Reviewed

    T. Kanemura, H. Sugiura, N. Yamaoka, S. Yoshihashi-Suzuki, H. Kondo, M. Ida, I. Matsushita, H. Horiik

    Fusion Engineering and Design   Vol. 86   page: 2462 - 2465   2011

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  76. Measurement of wavy surface Oscillations on liquid metal Lithium jet for IFMIF target Invited Reviewed

    H. Sugiura, T. Kanemura, S. Yoshihashi-Suzuki, H. Kondo, T. Yoshikawa, N. Yamaoka, M. Ida, H. Nakamura, I. Matsushita, H. Horiike

    Journal of Engineering for Gas Turbines and Power   Vol. 133   page: 052911 - 052917   2010

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  77. Matrix-Assisted laser desorption/ionization time-of-flight mass spectrometry using a mid-infrared tunable laser for direct protein analysis Invited Reviewed

    S. Yoshihashi-Suzuki, I. Sato, K. Awazu

    IEEE journal of selected topics in quantum electronics   Vol. 14   page: 113 - 117   2008

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  78. 中赤外波長可変固体レーザーを用いた新規質量分析装置によるタンパク質のイオン化 Invited Reviewed

    レーザー学会誌   Vol. 35   page: 382 - 387   2007

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  79. フェムト秒レーザーによるICG-PDTの基礎的検討(2) Invited Reviewed

    薬理と治療   Vol. 34   page: 107 - 112   2006

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  80. Medical application of an infrared free-electron laser: selective removal of cholesterol ester in carotid artery atheromatous plaques Invited Reviewed

    Journal of Neurosurgery   Vol. 104   page: 426 - 428   2006

  81. Medical application of an infrared free-electron laser: selective removal of cholesterol ester in carotid artery atheromatous plaques Invited Reviewed

    Journal of Neurosurgery   Vol. 104   page: 426 - 428   2006

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  82. 音響光学変調素子を用いた自由電子レーザーパルス制御装置の設計・開発 Invited Reviewed

    レーザー研究   Vol. 34   page: 369 - 373   2006

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  83. 中赤外自由電子レーザーによるコレステロールエステルの選択的除去 Invited Reviewed

    放射線   Vol. 31   page: 204 - 210   2005

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  84. Matrix-assisted laser desorption/ionization of protein samples containing a denaturant at high concentration using a mid-infrared free-electron laser(MIR-FEL) Invited Reviewed

    Y. Naito, S. Yoshihashi-Suzuki, K. Ishii, T. Kanai, K. Awazu

    International Journal of Mass Spectrometry   Vol. 241   page: 49 - 56   2005

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  85. フェムト秒レーザーによるICG-PDTの基礎的検討(1) Invited Reviewed

    粟津邦男, 鈴木幸子, 沢美喜, 大路正人, 田野保雄, 岩本由美子, 橋新裕一

    病理と治療   Vol. 32   page: 167 - 171   2004

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  86. UV/FEL-MALDI法を用いた不溶性タンパク質の質量分析 Invited Reviewed

    日本赤外線学会誌   Vol. 14   page: 57 - 62   2004

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  87. The effects of FEL irradiation against a phosphorylated peptide and the infrared spectrographic identification method for a phosohate group Invited Reviewed

    K. Ishii, S. Yoshihashi-Suzuki, K. Chihara, K. Awazu

    Nuclear Instruments and Methods in Physics Research A   Vol. 528   page: 614 - 618   2004

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  88. Improvement of matrix-assisted laser desorption/Ionization mass spectrometry using an infrared tunable free electron laser Invited Reviewed

    Y. Naito, S. Yoshihashi-Suzuki, K. Ishii, K. Awazu

    Nuclear Instruments and Methods in Physics Research A   Vol. 528   page: 609 - 613   2004

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  89. FT-IRによるリン酸化分析とその生体材料評価への応用 Invited Reviewed

    石井克典, 柳瀬薫, 鈴木-吉橋幸子, 山本雅哉, 千原國宏, 田畑泰彦, 粟津邦男

    日本赤外線学会誌   Vol. 14   page: 44 - 50   2004

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  90. 酸化ペプチドに対するFEL照射効果と赤外分光学的リン酸基判別法 Invited Reviewed

    石井克典, 鈴木-吉橋幸子, 千原國宏, 粟津邦男

    レーザー学会誌   Vol. 32   page: 43 - 47   2004

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  91. UV/FEL MALDI法による生体分子質量分析法 Invited Reviewed

    鈴木-吉橋幸子, 内藤康秀, 石井克典, 粟津邦男

    レーザー学会誌   Vol. 31   page: 841 - 848   2003

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  92. 硬化部位コレステロールの中赤外自由電子レーザーによる選択的除去 Invited Reviewed

    深見裕子, 鈴木-吉橋幸子, 粟津邦男

    レーザー学会誌   Vol. 31   page: 841 - 848   2003

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  93. Verification of Bi-directional Leader Concept by Interferometer Observation Invited Reviewed

    Journal of Atmospheric Electricity   Vol. 22   page: 55 - 79   2002

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  94. 干渉計による正極性落雷の三次元観測 Invited Reviewed

    電気学会論文誌B   Vol. 121-B   page: 357 - 363   2001

  95. 雷放電路三次元可視化とリーダ進展速度 Invited Reviewed

    吉橋幸子,河崎善一郎, 松浦虔士,磯田仁志, 園井康夫

    電気学会論文誌B   Vol. 120-B   page: 838 - 843   2000

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  96. Three dimensional imaging of lightning channenl and leader progression velovity Invited Reviewed

    Journal of Atmospheric Electricity   Vol. 20   page: 41 - 52   2000

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  97. 雷放電路三次元可視化とリーダ進展速度 Invited Reviewed

    吉橋幸子, 河崎善一郎, 松浦虔士, 磯田仁志, 園井康夫

    電気学会論文誌B   Vol. 120-B ( 6 ) page: 838 - 843   2000

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  98. 冬季雷と雲内放電進展様相 Invited Reviewed

    吉橋幸子,河崎善一郎, 松浦虔士,高木伸之, 渡辺貞司

    電気学会論文誌B   Vol. 119-B   page: 375 - 380   1999

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  99. UHF波帯干渉計を用いた多重落雷および多地点落雷観測結果 Invited Reviewed

    河崎善一郎,野村幸司, 吉橋幸子,松浦虔士

    電気学会論文誌B   Vol. 119-B   page: 614 - 619   1999

  100. 電波干渉計による夏季多重雷の三次元標定 Invited Reviewed

    吉橋幸子,大貫淳, 河崎善一郎,松浦虔士

    電気学会論文誌B   Vol. 119-B   page: 605 - 613   1999

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  101. UHF波帯干渉計を用いた多重落雷および多地点落雷観測結果 Invited Reviewed

    河崎善一郎, 野村幸司, 吉橋幸子, 松浦虔士

    電気学会論文誌B   Vol. 119-B ( 5 ) page: 614 - 619   1999

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  102. 電波干渉計による夏季多重雷の三次元標定 Invited Reviewed

    吉橋幸子, 大貫淳, 河崎善一郎, 松浦虔士

    電気学会論文誌B   Vol. 119-B ( 5 ) page: 605 - 613   1999

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  103. Lightning Activity During Winter Thunderstorm and Leader Progression in Thundercloud Invited Reviewed

    YOSHIHASHI Sachiko, KAWASAKI Zen-ichirou, MATSU-URA Kenji, TAKAGI Nobuyuki, WATANABE Teiji

    The Transactions of the Institute of Electrical Engineers of Japan. B A Publication of Power and Energy Society   Vol. 119-B ( 3 ) page: 375 - 380   1999

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    CiNii Books

  104. TRMM衛星搭載LISによる雷活動の観測 Invited Reviewed

    リモートセンシング学会誌   Vol. 18   page: 86 - 93   1998

▼display all

MISC 24

  1. BNCTの世界的な動向やもんじゅサイトに設置される試験研究炉への期待

    吉橋幸子

    原安協だより   Vol. 306   page: 1 - 6   2022.1

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    Authorship:Lead author  

  2. Nagoya University Accelerator-based Neutron Source (NUANS)

    Sachiko Yoshihashi, NUANS group

    Association of Asia Pacific Physical Societies Bulletin   Vol. 31   2021.6

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    Authorship:Lead author   Language:English   Publishing type:Article, review, commentary, editorial, etc. (scientific journal)  

  3. Gamma-ray Dosimetry in the BNCT Irradiation Field Using BeO Optically Stimulated Luminescence Dosimeter

    Watanabe Kenichi, Nakamura Satoru, Nagasaka Kosei, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2021.1   page: 576 - 576   2021.2

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    Language:Japanese  

    DOI: 10.11470/jsapmeeting.2021.1.0_576

  4. 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 講演予稿集     2021

  5. 名古屋大学におけるBNCT用加速器中性子源の開発

    土田一輝, 瓜谷章, 鬼柳善明, 西谷健夫, 吉橋幸子, 渡辺賢一, 山崎淳, 本田祥梧, 辻義之, 恒吉達也

    Isotope news   Vol. 777   page: 6 - 11   2021

  6. 名古屋大学におけるBNCT用加速器中性子源の開発

    土田一輝,瓜谷章, 鬼柳善明,西谷健夫, 吉橋幸子,渡辺賢一, 山崎淳,本田祥梧,辻義之,恒吉達也

    Isotope news   Vol. 777   page: 6 - 11   2021

  7. Output linearity and radiation resistance of an optical fiber-based neutron detector using Li-glass scintillator

    Ishikawa Akihisa, Yamazaki Atsushi, Watanabe Kenichi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2021.1   page: 555 - 55   2020.2

  8. Numerical Study of Turbulent Heat transfer enhancement in square-duct flow through of inline V-shaped discrete ribs

    Yu Stu. S, Tsuneyoshi T, Hamaji Y, Yoshihashi S, Ito T, Tsuji Y

    The Proceedings of Conference of Tokai Branch   Vol. 2020.69   page: 520   2020

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    DOI: 10.1299/jsmetokai.2020.69.520

  9. Crystal quality evaluation of TlBr by wavelength-resolved neutron imaging

    Watanabe Kenichi, Matsumoto Kio, Hitomi Keitaro, Nogami Mitsuhiro, Yamazaki Atsushi, Yoshihashi Sachiko, Uritani Akira

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.2   page: 519   2019.9

  10. Measurement of BNCT Neutron Field Using Optical Fiber-Based Neutron Detector

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

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.1 ( 0 ) page: 526 - 526   2019.2

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    Language:Japanese   Publisher:The Japan Society of Applied Physics  

    DOI: 10.11470/jsapmeeting.2019.1.0_526

    CiNii Research

  11. Improvement of the single edge fitting mode in the Bragg edge analysis code RITS

    Ohmae Kazuma, Watanabe Kenichi, Uritani Akira, Yamazaki Atsushi, Yoshihashi Sachiko, Kiyanagi Yoshiaki, Sato Hirotaka

    JSAP Annual Meetings Extended Abstracts   Vol. 2019.1 ( 0 ) page: 561 - 561   2019.2

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    Language:Japanese   Publisher:The Japan Society of Applied Physics  

    DOI: 10.11470/jsapmeeting.2019.1.0_561

    CiNii Research

  12. Research of Heat Transfer Enhancement in Turbulence Ribbed-duct Flow via Numerical simulation

    Yu Shichao, Tsuneyoshi Tatsuya, Hamaji Yukinori, Yoshihashi Sachiko, Ito Takahiro, Tsuji Yoshiyuki

    The Proceedings of Conference of Tokai Branch   Vol. 2019.68   page: 416   2019

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  13. Research of Heat Transfer Enhancement in Turbulence Ribbed-duct Flow via Numerical simulation

    Yu Shichao, Tsuneyoshi Tatsuya, Hamaji Yukinori, Yoshihashi Sachiko, Ito Takahiro, Tsuji Yoshiyuki

    The Proceedings of Conference of Tokai Branch   Vol. 2019.68   page: 416   2019

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    Language:English  

  14. 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

  15. What’s diversity for?

    Yoshida Hiroko, Yoshihashi Sachiko

    Journal of the Atomic Energy Society of Japan   Vol. 60 ( 5 ) page: 303 - 306   2018

  16. 大阪大学におけるほう素中性子捕捉療法装置

    堀池寛, 吉橋幸子

    電気設備学会誌   Vol. 34   page: 38 - 41   2014

  17. ダウンバーストの発生と雷放電の比較検証(3)

    吉橋幸子, 河崎善一郎, 藤吉康志, 新井健一郎, 大石英子

    日本気象学会大会講演予稿集   Vol. 79   page: 272 - 272   2001.5

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    Language:Japanese  

    CiNii Books

  18. ダウンバーストの発生と雷放電の比較検証(2)

    吉橋幸子, 川崎善一郎, 藤吉康志, 新井健一郎, 石原正仁

    日本気象学会大会講演予稿集   Vol. 78   page: 345 - 345   2000.10

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    Language:Japanese  

    CiNii Books

  19. 上向き放電で開始する落雷の極性依存性

    森本健志, 河崎善一郎, 吉橋幸子

    大気電気研究   Vol. 57 ( 57 ) page: 8 - 9   2000.10

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    Language:Japanese  

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  20. 雲内放電活動のUHF波帯干渉計による三次元像とレーダー観測結果の比較

    吉橋幸子, 河崎善一郎, 森本健志, 柴村孝嗣, 小林文明

    大気電気研究   Vol. 57 ( 57 ) page: 68 - 69   2000.10

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    Language:Japanese  

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  21. ダウンバーストの発生と雷放電の比較検証

    吉橋幸子, 川崎善一郎

    日本気象学会大会講演予稿集   Vol. 78   page: 345   1999.11

  22. TRMM/LIS Observations of Lightning Activity over Indonesia

    KAWASAKI Z-I.

    Proceeding of 11th International Conference on Atmospheric Electricity, 1999   Vol. 76   page: 207   1999.11

  23. 衛星による雷活動の観測

    河崎善一郎, 吉橋幸子

    月間海洋   Vol. 31 ( 6 ) page: 341 - 347   1999.6

  24. ダウンバーストの発生とSAFIR雷観測結果との照合

    吉橋幸子, 河崎善一郎, 石原正仁

    日本気象学会大会講演予稿集   Vol. 75   page: 155   1999.4

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▼display all

Presentations 59

  1. 核融合中性子源AーFNSによるBNCT用中性子場の核解析評価

    吉橋幸子、西谷健夫、権セロム、落合謙太郎、佐藤聡、山崎淳、瓜谷章

    第40回プラズマ・プラズマ核融合学会年会  2023.11.28 

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    Event date: 2023.11

    Language:Japanese   Presentation type:Oral presentation (general)  

  2. LHD重水素実験における誘導放射能の評価

    佐藤大地、吉橋幸子、山崎淳、小林真、西谷健夫、瓜谷章

    第40回プラズマ・核融合学会年会  2023.11.30 

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    Event date: 2023.11

    Language:Japanese   Presentation type:Oral presentation (general)  

  3. ホウ素中性子捕捉療法(BNCT)時における被ばく提言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 

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    Event date: 2023.11

    Presentation type:Poster presentation  

  4. 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、山崎淳、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

    Presentation type:Poster presentation  

  5. BNCTの適応拡大に向けた動物メラノーマ治療への基礎研究

    土本一貴、吉橋幸子、山崎淳、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:Oral presentation (general)  

  6. Evaluation of induced radioactivity generated in the LHD deuterium plasma experiments International conference

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

    30th International Toki Conference  2021.11.18 

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    Event date: 2021.11

    Language:English   Presentation type:Oral presentation (general)  

  7. hermal Neutron Measurement Capability of Single Crystal CVD Diamond Detector near the Reactor Core Region of UTR-KINKI

    M.I. Kobayashi, S. Yoshihashi, H. Yamanishi, S. Sangaroon, L. Ogawa, M. Isobe, A. Uritani, M. Osakabe

    30th International Toki Conference  2021.11.18 

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    Event date: 2021.11

    Language:English   Presentation type:Oral presentation (general)  

  8. Development of a pulse shape discrimination using single crystal CVD diamond detector for fast neutron measurement

    2021.9.9 

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    Event date: 2021.9

    Presentation type:Oral presentation (general)  

  9. Evaluation of Neutron Production by the p-Li Reaction for BNCT using ACE-J40HE

    2021.9.10 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

  10. Evaluation of induced radioactivity generated in the LHD deuterium experiments

    2021.9.9 

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    Event date: 2021.9

    Presentation type:Oral presentation (general)  

  11. Research on beam transport model construction of dynamitron accelerator for BNCT

    2021.9.8 

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    Event date: 2021.9

    Language:Japanese   Presentation type:Oral presentation (general)  

  12. Evaluation of beam scanning method for sealed Li target heat load reduction for BNCT

    2021.9.8 

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    Event date: 2021.9

    Presentation type:Oral presentation (general)  

  13. 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春の年会  2021.3.18 

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    Event date: 2021.3

  14. 光ファイバ型線量計作製の自動化およびその性能評価

    光ファイバ型線量計作製の自動化およびその性能評価

    日本原子力学会2021春の年会  2021.3.18 

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    Event date: 2021.3

  15. 光ファイバ型線量計作製の自動化およびその性能評価

    光ファイバ型線量計作製の自動化およびその性能評価

    日本原子力学会2021春の年会  2021.3.18 

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    Event date: 2021.3

    Presentation type:Oral presentation (general)  

  16. 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春の年会  2021.3.18 

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    Event date: 2021.3

    Presentation type:Oral presentation (general)  

  17. 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, 本田祥梧, 土田一輝, 渡辺賢一, 瓜谷章, 山崎淳

    日本原子力学会2021春の年会  2020.3.18 

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    Event date: 2021.3

    Presentation type:Oral presentation (general)  

  18. 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, 瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    第68回応用物理学会春季学術講演会  2021.3.17 

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    Event date: 2021.3

    Presentation type:Oral presentation (general)  

  19. 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

    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  2021.3.16 

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    Event date: 2021.3

    Presentation type:Oral presentation (general)  

  20. 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, 瓜谷章, 渡辺賢一, 吉橋幸子, 山崎淳

    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

    Presentation type:Oral presentation (general)  

  21. Neutron Source for BNCT at Nagoya University -High Current Operation- International conference

    S. Yoshihashi, K. Tsuchida, S. Honda, K. Watanabe, A. Yamazaki, A. Uritani, Y. Kiyanagi, Tsukasa Miyajima

    UCANS-web2020  2020.12.3 

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    Event date: 2020.11 - 2020.12

    Language:English   Presentation type:Oral presentation (general)  

    Venue:Online  

  22. A comprehensive evaluation of the thermal neutron detection efficiency by single crystal CVD diamond detector with LiF thermal neutron converter International conference

    Makoto I. Kobayashi, Sachiko Yoshihashi, Kunihiro Ogawa, Mitsutaka Isobe, Siriyaporn Sangaroon, Shuji Kamio, Yutaka Fujiwara, Masaki Osakabe

    31st Symposium on Fusion Technology  2020.9 

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    Event date: 2020.9

    Language:English   Presentation type:Poster presentation  

    Venue:Online  

  23. 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秋の年会  2020.9.17 

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    Event date: 2020.9

  24. 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秋の年会  2020.9.17 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

  25. 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秋の年会  2020.9.17 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:オンライン  

  26. 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秋の年会  2020.9.17 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

  27. BeO OSLを用いたBNCT場でのガンマ線線量測定手順に関する詳細検討

    中村悟, 瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    日本原子力学会2020秋の年会  2020.9.16 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

  28. 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, 瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    第81回応用物理学会秋季学術講演会  2020.9.8 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

  29. 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, 瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    第81回応用物理学会秋季学術講演会  2020.9.10 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

  30. 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  2020.9.10 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

  31. 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減の開発現状 Invited

    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  2020.9.10 

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:オンライン  

  32. 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  2020.9.9  応用物理学会

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    Event date: 2020.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:オンライン  

  33. 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, 瓜谷章, 渡辺賢一, 吉橋幸子, 山崎淳

    第81回応用物理学会秋季学術講演会  2020.9.11 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

  34. 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, 瓜谷章, 山崎淳

    第81回応用物理学会秋季学術講演会  2020.9.9 

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    Event date: 2020.9

    Presentation type:Oral presentation (general)  

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

    Kobayashi M.

    Journal of Instrumentation 

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    Event date: 2019.9

    Language:English   Presentation type:Oral presentation (general)  

    DOI: 10.1088/1748-0221/14/09/C09039

    Scopus

  36. LHDにおける放射化法を用いた中性子スペクトル測定

    田中智代、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、小林真

    原子力学会 2018年春の年会 

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    Event date: 2018.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  37. TRUST Eu:LiCAFを用いた一次元位置敏感型中性子検出器の特性評価

    志水裕昭、木野幸一、佐藤節夫、渡辺賢一、瓜谷章、吉橋幸子、山崎淳

    原子力学会 2018年春の年会 

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    Event date: 2018.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  38. 単一減速材球型中性子スペクトロメータを用いたBNCT中性子場のスペクトル測定に関する検討

    李思遠、佐藤和也、吉橋幸子、山崎淳、渡辺賢一、瓜谷章

    第65回応用物理学会 春季学術講演会 

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    Event date: 2018.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  39. LiF/Eu:CaF2共晶体シンチレータと光ファイバーを組み合わせた中性子検出器の特性評価

    渡辺賢一、石川諒尚、山崎淳、吉橋幸子、瓜谷章、河口範明、柳田健之

    日本中性子科学会第17回年会 

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    Event date: 2017.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  40. Examination of heat removal method of high heat flux to target International conference

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

    9th Young Researcher's BNCT Meeting 

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    Event date: 2017.11

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  41. Development of beam shaping assembly for BNCT system in Nagoya University International conference

    K. Sato, A. Uritani, K. Watanabe, S. Yoshihashi, A. Yamazaki, Y. Kiyanagi, K. Tsuchida

    9th Young Researcher's BNCT Meeting 

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    Event date: 2017.11

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  42. Accelerator based BNCT system in Nagoya University -Development of an Sealed Li target-

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  43. 名古屋大学における加速器BNCT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 

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    Event date: 2017.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  44. Neutron calibration experiment and the neutronics analysis for the deuterium plasma experiments on LHD International conference

    T. Nishitani, K. Ogawa, M. Isobe, H. Kawase, N. Pu, Y. Kashchuk, V. Krasilnikov, J Jo, M. Cheon, T. Tanaka, S. Yoshihashi, S. Li, M. Osakabe

    13th International Symposium on Fusion Nuclear Technology 

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    Event date: 2017.9

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  45. 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

    平田悠歩、山崎淳、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 (general)  

    Country:Japan  

  46. Optimization of imaging plate method for the measurement of activated indium as fast neutron detector in large radiation field International conference

    M.Kobayashi, T. Nishitani, T. Saze, T. Tanaka, S. Yoshihashi, K. Ogawa, M. Isobe

    9th International Symporium on Radiation Safety and Detection Technology 

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    Event date: 2017.7

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  47. Development of one-dimensional position-sensitive neutron detector using TRUST Eu:LiCAF scintillator International conference

    H. Shimizu, K. Kino, S Sato, K. Watanabe, A. Uritani, S. Yoshihashi, A. Yamazaki

    International Conference on Neutron Oprics (NOP2017) 

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    Event date: 2017.7

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  48. Improve design of the exit of a beam shaping assembly for an accelerator-driven BNCT system in Nagoya University International conference

    K. Sato, A. Uritani, K. Watanabe, S. Yoshihashi, A. Yamazaki, Y. Kiyanagi, K. Tsuchida

    International Conference on Neutron Oprics (NOP2017) 

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    Event date: 2017.7

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  49. Neutron Diagnostics in the Large Helical Device 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, S. Murakami, M. Osakabe, LHD Experiment group

    27th IEEE Symposium on Fusion Engineering 

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    Event date: 2017.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  50. Nagoya University BNCT system using DC accelerator and sealed lithium target International conference

    Sachiko Yoshihashi, A. Uritani, K. Watanabe, D. Furuzawa, K. Sato, K. Tsuchida, Y. Kiyanagi. G. Ichikawa, Y. Tsuji, T. Tsuneyoshi, Y. Hamaji

    Laser and Accelerator Neutron Sources and Applications 2017 

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    Event date: 2017.4

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  51. The design of the beam line of the Nagoya University accelerator-driven neutron source

    Ito I.

    Proceedings of Science 

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    Event date: 2017

    Language:English   Presentation type:Oral presentation (general)  

    Scopus

  52. Measurement of free-surface lithium flow using laser reflection method International conference

    Sachiko Yoshihashi, Kei Higashi, Eiji Hoashi, Takafumi Okita, Hiroo Kondo, Takuji Kanemura, Nobuo Yamaoka, Hiroshi Horiike

    29th symposium on fusion technology 

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    Event date: 2016.9

    Language:English   Presentation type:Poster presentation  

    Country:Czech Republic  

  53. Laser reflection measurement on liquid lithium slow surface flow International conference

    Sachiko Yoshihashi, Tsubasa Masaoka, Eiji Hoashi, Takafumi Okita, Hiroo Kondo, Takuji Kanemura, Nobuo Yamaoka, Hiroshi Horiike

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    Event date: 2014.9 - 2014.10

    Language:English   Presentation type:Poster presentation  

    Country:Spain  

  54. Optical measurement of the amount of evaporation of liquid metal lithium International conference

    Sachiko Yoshihashi, Noriyuki Teranishi, Kohei Yamamoto, Daisuke Izawa, Takafumi Okita, Eiji Hoashi, Hiroshi Horiike

    International Nuclear Target Development Society 2014 

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    Event date: 2014.8 - 2014.9

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  55. Mock-up Experiment at Birmingham University for BNCT Project of Osaka University -Gamma-ray Dose Measurement with Glass Dosimeter- International conference

    Sachiko Yoshihashi, Makoto Sakai, Masanobu manabe, Naoki Zushi, Shingo Tamaki, Isao Murata, Eiji Hoashi, Itsuro Kato, Shuhei Kuri, Shuji Oshiro, masao Nagasaki, Hiroshi Horiike

    16th International Congress on Neutron Capture Therapy 

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    Event date: 2014.6

    Language:English   Presentation type:Poster presentation  

    Country:Finland  

  56. Basic Research for decontamination and dismantlement of nuclear power plant structures using nano-pulsed laser International conference

    Sachiko Yoshihashi-Suzuki, Tomoko Kumakura, Eiji Hoashi, Hiroshi Horiike

    International Workshop on Laser Application to Nuclear Decommissioning and Decontamination LANDD2013 

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    Event date: 2013.12

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  57. Cut processing using short pulsed lasers for decomissioning International conference

    Sachiko Yoshihashi-Suzuki, Naoyuki Miyata, Tomoko Kumakura, Eiji Hoashi Hiroshi Horiike

    International Conference on Laser Applications in Nuclear Engineering 

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    Event date: 2013.4

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  58. BeO OSL線量計のBNCT場適用に向けた検討と特性評価

    中村悟, 瓜谷 章, 渡辺 賢一, 吉橋 幸子, 山﨑 淳

    日本放射線安全管理学会  2020.12.9 

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    Presentation type:Oral presentation (general)  

  59. 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  2020.11.14 

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    Presentation type:Oral presentation (general)  

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Research Project for Joint Research, Competitive Funding, etc. 12

  1. LHDの中性子応用に向けた高エネルギー荷電粒子計測システムの開発

    2019 - 2023.3

    核融合科学研究所 LHD計画共同研究  LHD計画共同研究

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    Authorship:Principal investigator 

    Grant amount:\25204000

  2. 重水素実験において生成されるLHD本体及び周辺機器の誘導放射能の評価

    2019 - 2023.3

    核融合科学研究所 LHD一般共同研究  LHD一般共同研究

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    Grant amount:\800000

  3. 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

    2022 - 2025

    医療機器開発推進研究事業 

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    Authorship:Coinvestigator(s)  Grant type:Competitive

  4. 核融合中性子源の医療応用に関する研究

    2022 - 2023.3

    国内共同研究 

  5. ホウ素中性子捕捉療法における家庭動物治療に関する基礎的研究

    2021 - 2022

    国内共同研究 

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    Authorship:Coinvestigator(s) 

    Grant amount:\1600000

  6. レーザー誘起ブレイクダウン分光法による小型中性子源用Liターゲットの表面状態観察

    2020.8 - 2021.3

    立松財団  特別研究助成

    吉橋幸子

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    Authorship:Principal investigator  Grant type:Competitive

    Grant amount:\3000000

  7. DNA二重鎖切断直接観察によるホウ素中性子捕捉療法の治療効果の定量評価

    2019 - 2022

    若手研究者による分野間連携研究プロジェクト 

  8. LHD重水素実験のためのMeVイオン計測システムの開発

    2016.6 - 2017

    国内共同研究 

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    Authorship:Coinvestigator(s)  Grant type:Competitive

  9. 加速器BNCT用ターゲットの除熱性能評価試験

    2016.6 - 2017

    国内共同研究 

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    Authorship:Coinvestigator(s)  Grant type:Competitive

  10. ホウ素中性子捕捉療法(BNCT)の中性子発生装置に関する研究開発

    2016 - 2018

    医療機器開発推進研究事業 

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    Authorship:Coinvestigator(s) 

  11. 原子炉等大型構造材向け高輝度レーザーによる非熱加工の基礎研究

    2012 - 2013

    関西原子力懇談会学術振興奨学金寄付金 

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    Authorship:Principal investigator 

  12. JT-60SAにおけるシンセティック中性子計測の構築

    国内共同研究 

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KAKENHI (Grants-in-Aid for Scientific Research) 19

  1. 重水素実験において生成されるLHD本体及び周辺機器の誘導放射能の評価

    2019 - 2023.3

    自然科学研究機構 核融合科学研究所  核融合科学研究所 LHD一般共同研究  LHD一般共同研究

  2. LHDの中性子応用に向けた高エネルギー荷電粒子計測システムの開発

    2019 - 2023.3

    自然科学研究機構 核融合科学研究所  核融合科学研究所 LHD計画共同研究  LHD計画共同研究

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    Authorship:Principal investigator 

    Grant amount:\25204000

  3. Development of innovative electromagnetic pump using permanent magnet

    Grant number:16K14541  2016.4 - 2019.3

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Challenging Exploratory Research

    Yoshihashi Sachiko, SUNAGAWA Takeyoshi, SUNAGAWA Takeyoshi

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    Authorship:Principal investigator 

    Grant amount:\3510000 ( Direct Cost: \2700000 、 Indirect Cost:\810000 )

    This challenge is a basic study of the development of a small electromagnetic pump for flowing liquid metal.Liquid metal flow is used for fusion reactors and fast reactors, and in recent years as targets for small neutron sources.However, typical electromagnetic pumps used for liquid metal flow are large and complex.In this study, we formulated and built a pump that combines two small permanent magnet arrays.First, the magnetic field distribution was calculated by numerical analysis, the magnetic field of the pump was measured with a gauss meter, and the consistency between the calculation result and the experimental value was confirmed.Next, the thrust was measured using different types of metal plates, and the relationship between the electrical conductivity and the thrust was evaluated.As the results, we succeeded in demonstrating the principle of this pump.

  4. Direct protein analysis from electrophoresis gel using a mid-infrared laser

    Grant number:20750062  2008 - 2009

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Young Scientists (B)

    SUZUKI Sachiko

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    Authorship:Principal investigator 

    Grant amount:\4030000 ( Direct Cost: \3100000 、 Indirect Cost:\930000 )

    In this study, I performed protein analysis from acrlamide gel after electrophoresis using a Mid-infrared tunable laser. I reported that the IR-MALDI process is influenced by the hydrogen bond around the carboxyl group or residual water. The aclylamide solution has a strong absorption bands at around 6.0μm correstponding to the >C=O stretching vibration mode. I obtained the mass spectrum of insulin ionized from acrylamide gel when the sample was irradiated by the infrared laser in a wavelength range of 5.8-5.9μm.

  5. 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

    2022 - 2025

    医療機器開発推進研究事業 

      More details

    Authorship:Coinvestigator(s)  Grant type:Competitive

  6. 核融合中性子源の医療応用に関する研究

    2022 - 2023.3

    国立研究開発法人量子科学魏y術研究開発機構  国内共同研究 

  7. ホウ素中性子捕捉療法における家庭動物治療に関する基礎的研究

    2021 - 2022

    国内共同研究 

      More details

    Authorship:Coinvestigator(s) 

  8. レーザー誘起ブレイクダウン分光法による小型中性子源用Liターゲットの表面状態観察

    2020.8 - 2021.3

    公益財団法人  立松財団  特別研究助成

    吉橋幸子

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    Authorship:Principal investigator  Grant type:Competitive

    Grant amount:\3000000

  9. DNA二重鎖切断直接観察によるホウ素中性子捕捉療法の治療効果の定量評価

    2019 - 2022

    若手研究者による分野間連携研究プロジェクト 

  10. 加速器BNCT用ターゲットの除熱性能評価試験

    2016.6 - 2017

    自然科学研究機構 核融合科学研究所  国内共同研究 

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    Authorship:Coinvestigator(s)  Grant type:Competitive

  11. LHD重水素実験のためのMeVイオン計測システムの開発

    2016.6 - 2017

    自然科学研究機構 核融合科学研究所  国内共同研究 

      More details

    Authorship:Coinvestigator(s)  Grant type:Competitive

  12. ホウ素中性子捕捉療法(BNCT)の中性子発生装置に関する研究開発

    2016 - 2018

    医療機器開発推進研究事業 

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    Authorship:Coinvestigator(s) 

  13. Development of real-time T/N ratio measuring technique for BNCT

    Grant number:15H04242  2015.4 - 2019.3

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Scientific Research (B)

    Murata Isao

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    Authorship:Coinvestigator(s) 

    Boron Neutron Capture Therapy (BNCT) is known as a promising radiation cancer therapy. For the realization, a special SPECT system is indispensable to know the BNCT effect by monitoring T/N Ratio (concentration ratio of 10B in tumor to normal cell) in realtime. In this study, basic researches for the T/N-SPECT were carried out. First, we investigated an elemental device to detect 478 keV γ-rays emitted from BNC reaction, and decided to use GAGG scintillator as the key detection element for T/N-SPECT. Then, we aimed to carry out the performance test by using an epi-thermal neutron source produced with a DT neutron source. However, due to the Northern Osaka Earthquake the accelerator was seriously broken so that it became not possible to carry out experiments. Instead we utilized an AmBe source to prepare an epi-thermal neutron source, though it was a little weak. We confirmed only the basic validity. We think, we should do more precise experiments using the DT neutron source in future.

  14. Study on new concept for control of liquid metal jet

    Grant number:24561025  2012.4 - 2015.3

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Scientific Research (C)

    HOASHI Eiji, HORIIKE Hiroshi, KIMURA Haruyuki, SUZUKI Sachiko, YAMAOKA Nobuo, HORIIKE Hiroshi, KIMURA Haruyuki, SUZUKI Sachiko, YAMAOKA Nobuo

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    Authorship:Coinvestigator(s) 

    For liquid metal lithium jet used as a beam target in accelerator-based neutron source such as IFMIF, we proposed innovative magnetically guided liquid metal target (MGLT), which enable us to control liquid metal jet using magnetic field, and demonstrated the performance of MGLT using two dimensional simulation. In this demonstration, we showed that interaction coefficient, which was the ratio of the inertia force with the electormagnetic force, was effective to get the condition for curving liquid metal jet by magnetic field. Next, we optimized the size and the shape of MGLT for gallium jet, which is the alternative liquid metal to lithium, used in our substantiative experiment. In addition, using simulation, we obtained experimental conditions of gallium jet and demonstrated the performance of MGLT for gallium jet. Finally, based on these results of simulation, we designed and made gallium test loop.

  15. 原子炉等大型構造材向け高輝度レーザーによる非熱加工の基礎研究

    2012 - 2013

    関西原子力懇談会学術振興奨学金寄付金 

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    Authorship:Principal investigator 

  16. Extended research related to the direct observation and control of liquid metal flow dynamics

    Grant number:22246129  2010.5 - 2014.3

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Scientific Research (A)

    FUKUDA Takeshi, HORIIKE Hiroshi, TAKATA Takashi, SUZUKI Sachiko, KAMIDE Hideki, KIMURA Nobuyuki, HORIIKE Hiroshi, TAKATA Takashi, SUZUKI Sachiko, KAMIDE Hideki, KIMURA Nobuyuki

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    Authorship:Coinvestigator(s) 

    As a bona fide extension of the exploratory work, where direct observation and active control of sodium flow dynamics have first been proposed using coherent VUV radiation, we have further extended its engineering capability to demonstrate that the proven proposition of 'transparent sodium' is practically applicable to reactor-relevant conditions, and spatial resolution of the velocity field measurement could also be improved sufficiently for comparison with large-scale simulation results. The ab-initio calculations have also been carried out. As a replacement of the emission from the induced Raman scattering, an electron-beam excited Ar excimer source has been employed, which has substantially increased the signal intensity. In addition, an imaging spectrometer has been introduced to identify the optical components from the trace graphite particles. Consequently, it was shown that the 2D liquid sodium flow velocity field could be resolved within the resolution of a few mm.

  17. Measurement of organic metabolism using low-energy photons

    Grant number:19056003  2007 - 2011

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Scientific Research on Priority Areas

    AWAZU Kunio, HAZAMA Hisanao, ISHII Katsunori, HAZAMA Hisanao, ISHII Katsunori

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    Authorship:Coinvestigator(s) 

    Matrix-assisted laser desorption/ionization (MALDI) mass spectrometry is widely used in the analysis of biomolecules such as proteins. However, the mechanism of MALDI has not been fully understood. If the MALDI process is elucidated and controlled, further progress in the biomedical fields is expected. In this study, we have used a mid-infrared laser instead of a conventional ultraviolet laser for MALDI and have succeeded in ionizing an insoluble analyte which has been hard to ionize. In addition, we have found that the wavelength dependence of the ionization efficiency of peptides is correlated with the chemical structure of the matrix and that the water solvent has influence on the ionization with MALDI.

  18. Fundamental research of non-thermal process using free electron laser with short pulses

    Grant number:19206103  2007 - 2010

    Japan Society for the Promotion of Science  Grants-in-Aid for Scientific Research  Grant-in-Aid for Scientific Research (A)

    HORIIKE Hiroshi, FUKUDA Takeshi, SUZUKI Sachiko, YAMAOKA Nobuo, MINEHARA Eisuke, MIYAMOTO Seiji, KONDO Hiroo, FUKUDA Takeshi, SUZUKI Sachiko, YAMAOKA Nobuo, MINEHARA Eisuke, MIYAMOTO Seiji, KONDO Hiroo

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    Authorship:Coinvestigator(s) 

    An experimental research was performed on the non-thermal processing of heavy and thick structure materials like a nuclear reactor vessel and nuclear fuel assembly, with using highly coherent and intense free electron laser (FEL) of pico-second pulses. Zircaloy4 alloy plates, which is material of fuel tube were tried and cut with FEL, and a state-of-art commercially available laser. The comparison of these showed that with FEL, very narrow-width efficient non-thermal processing is possible for those structure materials. Fundamental conditions for narrow processing or cutting were verified with using a nano-second pulse laser. As a result, technical specifications of laser lights and of optical systems for light guiding, were revealed and confirmed experimentally.

  19. JT-60SAにおけるシンセティック中性子計測の構築

    国立研究開発法人量子科学技術研究開発機構  国内共同研究 

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Teaching Experience (On-campus) 22

  1. Numerical Analysis

    2020

  2. Mathematics II and Tutorial

    2020

  3. Computer Programing and Numerical Calculation B

    2020

  4. Engineering Mathematics II with Exercises

    2020

  5. 総合エネルギー工学セミナー2B

    2020

  6. 総合エネルギー工学セミナー2A

    2020

  7. 総合エネルギー工学特別実験及び演習B

    2020

  8. 総合エネルギー工学特別実験及び演習A

    2020

  9. 中性子・原子核科学

    2020

  10. 総合エネルギー工学セミナー1D

    2020

  11. 総合エネルギー工学セミナー1C

    2020

  12. 総合エネルギー工学セミナー1B

    2020

  13. 総合エネルギー工学セミナー1A

    2020

  14. エネルギー理工学特別講義第2

    2020

  15. エネルギー理工学セミナーB

    2020

  16. エネルギー理工学輪講A

    2020

  17. 卒業研究B

    2020

  18. 総合エネルギー工学セミナー2C

    2020

  19. 総合エネルギー工学セミナー2E

    2020

  20. 総合エネルギー工学セミナー2D

    2020

  21. 中性子原子核科学特論

    2016

  22. 基礎セミナーB

    2016

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Teaching Experience (Off-campus) 26

  1. 総合エネルギー工学特別実験及び演習B

    2020 Nagoya University)

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    Level:Postgraduate 

  2. 卒業研究B

    2020 Nagoya University)

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    Level:Undergraduate (specialized) 

  3. Engineering Mathematics II with Exercises

    2020 Nagoya University)

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    Level:Undergraduate (specialized) 

  4. 中性子・原子核科学

    2020 Nagoya University)

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    Level:Postgraduate 

  5. Computer Programing and Numerical Calculation B

    2020 Nagoya University)

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    Level:Undergraduate (specialized) 

  6. 総合エネルギー工学特別実験及び演習A

    2020 Nagoya University)

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    Level:Postgraduate 

  7. 総合エネルギー工学セミナー2E

    2020 Nagoya University)

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    Level:Postgraduate 

  8. 総合エネルギー工学セミナー2D

    2020 Nagoya University)

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    Level:Postgraduate 

  9. 総合エネルギー工学セミナー2C

    2020 Nagoya University)

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    Level:Postgraduate 

  10. 総合エネルギー工学セミナー2B

    2020 Nagoya University)

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    Level:Postgraduate 

  11. 総合エネルギー工学セミナー2A

    2020 Nagoya University)

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    Level:Postgraduate 

  12. 総合エネルギー工学セミナー1D

    2020 Nagoya University)

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    Level:Postgraduate 

  13. 総合エネルギー工学セミナー1C

    2020 Nagoya University)

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    Level:Postgraduate 

  14. 総合エネルギー工学セミナー1B

    2020 Nagoya University)

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    Level:Postgraduate 

  15. 総合エネルギー工学セミナー1A

    2020 Nagoya University)

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    Level:Postgraduate 

  16. Mathematics II and Tutorial

    2020 Nagoya University)

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    Level:Undergraduate (specialized) 

  17. Numerical Analysis

    2020 Nagoya University)

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    Level:Undergraduate (specialized) 

  18. エネルギー理工学セミナーB

    2020 Nagoya University)

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    Level:Undergraduate (liberal arts) 

  19. エネルギー理工学特別講義第2

    2020 Nagoya University)

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    Level:Undergraduate (liberal arts) 

  20. エネルギー理工学輪講A

    2020 Nagoya University)

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    Level:Undergraduate (specialized) 

  21. 中性子原子核科学特論

    2016 Nagoya University)

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    Level:Postgraduate 

  22. 基礎セミナーB

    2016 Nagoya University)

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    Level:Undergraduate (liberal arts) 

  23. 放射線生物学

    2015.4 - 2016.3 Fukui University of Technology)

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    Level:Undergraduate (specialized) 

  24. 量子エネルギー基礎論

    2015.4 - 2015.3 Osaka University)

  25. 電磁気学

    2010.4 - 2015.3 Osaka University)

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    Level:Undergraduate (specialized) 

  26. 電力工学

    2010.4 - 2015.3 Osaka University)

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Social Contribution 7

  1. 興味を持って学びたくなる放射線の基礎知識

    Role(s):Lecturer

    中部原子力懇談会  エネルギー・環境研究会  2022.7

  2. 低炭素社会に向けた日本のエネルギー問題

    Role(s):Lecturer

    しずおかオンライン、静岡エネルギー・環境懇談会  2022.7

  3. 放射線の基礎知識(放射性物質の事故対策)

    Role(s):Lecturer

    岐阜県消防学校、中部原子力懇談会  2022.1

  4. エネルギー理工学科で医療研究?細胞レベルでがんを治す放射線治療

    Role(s):Lecturer

    名古屋大学  テクノ・シンポジウム名大in長野  2019.12

  5. 放射線の基礎知識(放射性物質の事故対策)

    Role(s):Lecturer

    岐阜県消防学校、原子力安全協会  2019.11

  6. 放射線で診て治す!放射線治療の現状

    Role(s):Lecturer

    河合塾  名大研究室の扉in河合塾  2017.6

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    Audience: High school students

    Type:Lecture

  7. 原子の力でがんを狙い撃つ!

    Role(s):Lecturer

    夢ナビライブ2021 

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