研究者詳細 - 吉橋　幸子

論文 - 吉橋　幸子

分割表示 108 件中 21 - 40 件目／全件表示 >>

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

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

PLASMA AND FUSION RESEARCH 17 巻 ( 0 ) 頁： 2405045 - 2405045 2022年6月

記述言語：英語掲載種別：研究論文（学術雑誌）出版者・発行元：一般社団法人プラズマ・核融合学会

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 6LiF 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 × 106 n cm−2 s−1 W−1 up to a reactor power of 1W.

DOI： 10.1585/pfr.17.2405045

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

Kobayashi, MI; Yoshihashi, S; Ogawa, K; Isobe, M; Sangaroon, S; Kamio, S; Fujiwara, Y; Osakabe, M

FUSION ENGINEERING AND DESIGN 179 巻 2022年6月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Fusion Engineering and Design

Thermal neutron detection efficiency of the single crystal CVD diamond detector (SDD) equipping 1.9 μm-thick 6LiF thermal neutron converter, which induces the energetic ions through the 6Li(n,α)3H reaction, was evaluated comprehensively using a charge-integral based pulse shape discrimination (PSD) method and radiation transport calculation by PHITS. The PSD method applied in this work successfully separated the pulses induced by energetic tritons, alpha particles and other types of radiation. The detection efficiency of tritons was consistent with the radiation transport calculation, although that of alpha particles was lower than the estimation. The overall thermal neutron detection efficiency was obtained by summing detection efficiencies of tritons and alpha particles. Approximately 29% of 6Li(n,α)3H reaction occurred in an effective 1.9 μm-thick 6LiF thermal neutron converter could be detectable as the pulses of tritons (∼ 73%) and alpha particles (23%).

DOI： 10.1016/j.fusengdes.2022.113117

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

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

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 59 巻 ( 5 ) 頁： 605 - 613 2022年5月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Journal of Nuclear Science and Technology

The lithium thick target bombed with low-energy protons is one of the promising neutron sources for the Boron Neutron Capture Therapy (BNCT). The benchmark calculations of the neutron Thick Target Yield (TTY) of the lithium target are conducted by the Particle and Heavy Ion Transport Code System PHITS with ACE formatted files of JENDL-4.0/HE and ENDF/B-VII and the DROSG-2000 code for the incident proton energy of around 3 MeV. Also, neutron TTY of the lithium thick target with a titanium window is evaluated for the Nagoya University Accelerator-driven Neutron Source (NUANS). Finally, the TTY evaluated with PHITS is applied for the neuron transport calculation for the Beam Shaping Assembly (BSA) of NUANS. As a conclusion, it is considered that ENDF/B-VII is more feasible than JENDL-4.0/HE for the 7Li(p,n)7Be reaction around 3 MeV of the proton energy.

DOI： 10.1080/00223131.2021.1996297

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

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

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 59 巻 ( 4 ) 頁： 534 - 541 2022年4月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Journal of Nuclear Science and Technology

The D(d, n)3He reaction is one of the common monoenergetic neutron sources. We compile the Frag Data table of D(d, n)3He reaction from the literature as an external cross-section data for PHITS. We confirm the validity of the Frag Data table by the calculation of the total and angular neutron yield calculations for an ideal deuterium thin target. Finally, PHITS with the Frag Data table is applied to the angular neutron yield and spectrum calculations of the gas target and the deuterium-loaded titanium target of the Tohoku University Fast Neutron Laboratory.

DOI： 10.1080/00223131.2021.1981475

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

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

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 1025 巻 2022年2月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

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

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

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

PLASMA AND FUSION RESEARCH 16 巻 ( 0 ) 頁： 1405104 - 1405104 2021年11月

記述言語：英語掲載種別：研究論文（学術雑誌）出版者・発行元：一般社団法人プラズマ・核融合学会

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

DOI： 10.1585/pfr.16.1405104

BeO光刺激蛍光体を用いたBNCT場でのガンマ線線量評価

渡辺賢一, 中村悟, 永坂光正, 山﨑淳, 吉橋幸子, 瓜谷章

応用物理学会学術講演会講演予稿集 2021.1 巻 ( 0 ) 頁： 576 - 576 2021年2月

BeO光刺激蛍光体を用いたBNCT場でのガンマ線線量評価

渡辺賢一, 中村悟, 永坂光正, 山﨑淳, 吉橋幸子, 瓜谷章

応用物理学会学術講演会講演予稿集 2021.1 巻 ( 0 ) 頁： 576 - 576 2021年2月

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

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

APPLIED RADIATION AND ISOTOPES 168 巻頁： 109553 2021年2月

記述言語：英語掲載種別：研究論文（学術雑誌）出版者・発行元：Elsevier

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 ⁶LiF/Eu:CaF₂ 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) × 10⁷ n/(cm2 s).

DOI： 10.1016/j.apradiso.2020.109553

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

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

FUSION ENGINEERING AND DESIGN 161 巻 2020年12月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Fusion Engineering and Design

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

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 Open Access

Fujimura, A; Yasui, S; Igawa, K; Ueda, A; Watanabe, K; Hanafusa, T; Ichikawa, Y; Yoshihashi, S; Tsuchida, K; Kamiya, A; Furuya, S

CELLS 9 巻 ( 10 ) 2020年10月

記述言語：英語掲載種別：研究論文（学術雑誌）出版者・発行元：Cells

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 CD44High 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 CD44High 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.

DOI： 10.3390/cells9102149

Observation of neutron emission anisotropy by neutron activation measurement in beam-injected LHD deuterium plasmas Open Access

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

NUCLEAR FUSION 60 巻 ( 7 ) 2020年7月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Nuclear Fusion

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

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 133 巻 2020年4月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Radiation Measurements

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

Liガラスシンチレータを用いた光ファイバ型中性子検出器の出力線形性および放射線耐性

石川諒尚, 山﨑淳, 渡辺賢一, 吉橋幸子, 瓜谷章

応用物理学会学術講演会講演予稿集 2020.1 巻 ( 0 ) 頁： 555 - 555 2020年2月

Liガラスシンチレータを用いた光ファイバ型中性子検出器の出力線形性および放射線耐性

石川諒尚, 山﨑淳, 渡辺賢一, 吉橋幸子, 瓜谷章

応用物理学会学術講演会講演予稿集 2021.1 巻 ( 0 ) 頁： 555 - 55 2020年2月

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

Watanabe, K; Mitsuboshi, N; Ishikawa, A; Yamazaki, A; Yoshihashi, S; Uritani, A; Kawaguchi, N; Yanagida, T; Fukuda, K

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 954 巻 2020年2月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

We developed a mixed powder neutron scintillator as a novel neutron detection material. Since LiF-Ag:ZnS mixed powder, which is a widely used mixed powder neutron scintillator, is opaque owing to the extremely high refractive index of Ag:ZnS, the scintillator thickness is limited. We proposed the use of LiF-Eu:CaF2 mixed powder, where both LiF and Eu:CaF2 have almost the same refractive index, as a roughly transparent mixed powder neutron scintillator. Although the just mixed LiF-Eu:CaF2 powder is opaque, it can become translucent by filling the gap in the powder with a liquid glass resin as a refractive index buffer. As a result, we observe a peak shape in the pulse height spectrum obtained from the LiF-Eu:CaF2 mixed powder scintillator when irradiating thermal neutrons.

DOI： 10.1016/j.nima.2018.09.079

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

Ishikawa, A; Yamazaki, A; Watanabe, K; Yoshihashi, S; Uritani, A; Fukuda, K; Koike, A; Ogawara, R; Suda, M; Hamano, T

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT 954 巻 2020年2月

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

We developed optical fiber-based neutron detectors that use small pieces of6Li-based scintillators, namely, Eu:LiCaAlF6 crystals and LiF/Eu:CaF2 eutectics. Considering that these elements have high light yields (more than 10,000 photons/neutron), they can produce pulse height spectra with clear peaks even when using optical fiber light guides. To adjust the neutron sensitivity, we controlled the amount of6Li in the scintillator. We fabricated three different detectors using Eu:LiCaAlF6 and LiF/Eu:CaF2 with various amounts of6Li and then evaluated the neutron sensitivity of each detector. This approach confirmed that there was a linear relationship between the neutron sensitivity and amount of6Li, thus implying that the6Li mass measured by a high-precision balance could be a good metric of neutron sensitivity. We also checked the linearity of the output of the detector at relatively high neutron fluxes by using an accelerator-based neutron source. Although the detectors showed saturation behavior at high count rate, we were able to cover a relatively wide dynamic range by combining multiple detectors using different amounts of6Li. After correcting for the pulse height distortion and count loss due to pile-up events, we were able to confirm the linearity of the detectors up to a count rates of 100 kcps.

DOI： 10.1016/j.nima.2018.11.120

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 2020.69 巻 ( 0 ) 頁： 520 2020年

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

Kobayashi, MI; Ogawa, K; Isobe, M; Nishitani, T; Nishimura, T; Mukai, K; Yoshihashi, S; Osakabe, M

PLASMA AND FUSION RESEARCH 15 巻 ( 0 ) 頁： 2405043 - 2405043 2020年

記述言語：英語掲載種別：研究論文（学術雑誌）出版者・発行元：一般社団法人プラズマ・核融合学会

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, epithermal 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.

DOI： 10.1585/pfr.15.2405043

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

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

SENSORS AND MATERIALS 32 巻 ( 4 ) 頁： 1489 - 1495 2020年

記述言語：日本語掲載種別：研究論文（学術雑誌）出版者・発行元：Sensors and Materials

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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