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藤 暢輔; 大図 章; 土屋 晴文; 古高 和禎; 北谷 文人; 米田 政夫; 前田 亮; 小泉 光生
EPJ Web of Conferences, 329, p.06001_1 - 06001_4, 2025/06
There is no acceptable and practicable single nondestructive method for the assay of Special Nuclear Materials (SNM) and Minor Actinides (MA) in highly radioactive nuclear materials. The Japan Atomic Energy Agency (JAEA) and the Joint Research Centre (JRC) of the European Commission have been developing an active neutron nondestructive assay (NDA) system for nuclear non-proliferation and nuclear security. We utilize four different NDA techniques, namely Differential Die-Away Analysis (DDA), Prompt Gamma-ray Analysis (PGA), Neutron Resonance Transmission Analysis (NRTA) and Delayed Gamma-ray Analysis (DGA). The techniques give us different and useful analytical results, which could provide complementary information. We developed a combined NDA system, which enables the simultaneous measurements of DDA and PGA in the first phase of the collaboration. The improved DDA is possible to quantify a small amount of the fissile mass as low as 1mg (Pu-239). In the second phase, we developed an advanced NDA system which allows us to measure by NRTA as well as DDA and PGA. The third phase has started to study a compact NRTA system from 2022 for four years. NRTA would be the most promising method for highly radioactive nuclear materials. An overview of the projects and the recent results will be presented. This research was implemented under the subsidiary for nuclear promotion of MEXT (the Ministry of Education, Culture, Sports, Science and Technology of Japan).
瀬川 麻里子; 藤 暢輔; 前田 亮; 甲斐 哲也
Journal of Nuclear Science and Technology, 62(3), p.268 - 277, 2025/03
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)Degerming temperatures with small uncertainties is important for neutron thermometry, required for both fundamental science and industrial applications. Conventionally, neutrons transmitted through a sample in shielded materials are detected. The sample temperature is then derived by analyzing the energy dependence of the transmission neutrons at resonances influenced by the Doppler-broadening effect. However, reducing the temperature-determination uncertainty is extremely hard with the conventional method, because it is determined only by the small changes at the resonances, i.e. temperature-sensitive components, compared to the primary neutrons. Therefore, we propose a new thermometry method named neutron self-indication thermometry (NSIT), which combines the Doppler-broadening effect with a self-indication technique that irradiates the sample and an indicator containing the same nuclide as the sample. The NSIT can enhance temperature sensitivity by measuring prompt gamma-rays to indirectly obtain the temperature-sensitive components at resonances by employing the same resonance twice. This study compared the temperature sensitivity and uncertainty of the conventional and NSIT methods by varying the sample temperatures from 23.0
C to 492.6C. The results demonstrated that the NSIT was approximately 1.6 times more sensitive and had lower uncertainty in determining temperature. These findings highlight the potential of the NSIT as an effective alternative to remote thermometry.
田辺 鴻典*; 米田 政夫; 藤 暢輔; 北村 康則*; 三澤 毅*
日本原子力学会誌ATOMO
, 67(3), p.198 - 202, 2025/03
鉛等で隠匿された
Uに対する非破壊測定技術の開発は、長年、核セキュリティ上の最重要課題と言われてきたが、依然として現場レベルでの検知は困難な状況にある。我々は
Cf回転照射法と呼ばれる新たな核物質非破壊測定手法を提案し、回転照射装置と水チェレンコフ中性子検出器で構成される運搬性の高い現場検知システムを開発、本システムによる核物質検知を実証した。本報では、開発したシステムを概説するとともに今後の展望について解説する。
石川 諒尚; 瀬川 麻里子; 藤 暢輔; 渡辺 賢一*; 増田 明彦*; 松本 哲郎*; 山崎 淳*; 吉橋 幸子*; 瓜谷 章*; 原野 英樹*
Journal of Radiation Research (Internet), p.rraf048_1 - rraf048_7, 2025/00
被引用回数：0 パーセンタイル：0.00An optical fiber-based neutron detector is a real-time neutron monitor for an intense neutron field. A small piece of neutron scintillator, such as Ce-doped lithium glass (Li-glass), used in the detector has a random shape with a grain size of 200-400 
m. This causes shape-dependent effects on the detector response. However, it is difficult to control or clarify the micro shape due to its small size. Here we propose a technique to obtain the fine structure of a small piece of the scintillator using a microcomputed tomography (CT) system. To verify accuracy, the mass estimated based on the volume extracted from the obtained CT image was compared to the mass measured in advance using an electronic balance. In the obtained CT images, the fine shape of the small piece of Li-glass was clearly visible, and no false signals from the surrounding components were observed. The estimated mass was in good agreement with the measured value, however, a slight underestimation was observed when the total number of projection images was 2000. This was mitigated by increasing the number of projection images, and the difference between the estimated and measured mass was 1.6% when the number of the projection images was 3141. This was equivalent to the uncertainty of the measured mass. The proposed technique will be useful when high accuracy is needed, such as for medical applications.
前田 亮; 米田 政夫; 藤 暢輔
Nuclear Science and Engineering, 14 Pages, 2025/00
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)In the decommissioning of the Fukushima Daiichi Nuclear Power Plant (1F), since objects removed from the Primary Containment Vessel (PCV) include not only fuel debris containing nuclear materials but also structural materials, it is not necessarily reasonable to treat all of them as fuel debris. Hence, it is important to establish a method for sorting of 1F fuel debris according to the quantity of nuclear materials present. However, the fuel debris may melt and mix with the control rods, which are neutron absorbers, making it difficult to apply conventional nondestructive measurement methods using neutrons. This study evaluates the performance of the Fast Fission neutron Coincidence Counting (FFCC) method, a nondestructive measurement method of nuclear materials that is less affected by neutron absorbers utilizing fast fission and fast coincidence on the order of nano second. Experimental results with a simple measurement system indicate that the FFCC method can detect significantly lower amounts of uranium than the sorting criteria, even in the presence of a substantial amount of neutron absorber, demonstrating high quantitativity. Optimization of the measurement system can lead to a dramatic enhancement of its capabilities. Therefore, the FFCC method is considered a promising technique for the sorting of 1F fuel debris.
Ir at ANNRI MLF J-PARCPatwary, K.; 瀬川 麻里子; 前田 亮; 藤 暢輔; 遠藤 駿典; 中村 詔司; Rovira Leveroni, G.; 木村 敦
Journal of Nuclear Science and Technology, 61(10), p.1385 - 1396, 2024/10
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)Thermal neutron capture cross-section for Ir, 
(E
), is a prominent parameter in producing 
Ir radionuclide used in high-dose-rate brachytherapy. However, considerable discrepancies exist in past measurements using the activation method and a derived cross-section data calculation from positive resonance parameters of Ir, which were measured using the neutron time-of-flight (TOF) method. Therefore, for the first time, we aimed to measure the (E) accurately using the neutron TOF method. Experiments were performed using a pulsed neutron beam and a NaI(Tl) detector at the Accurate Neutron-Nucleus Reaction Measurement Instrument of the Materials and Life Science Experimental Facility in the J-PARC. The (E) was derived from the capture yield using the pulse height weighting technique. As a result, this study obtained the (E) as 949 
80 b. The result agrees with some activation data and the evaluated nuclear data libraries, JENDL-5 and ENDF/B-VIII.0, within its uncertainty of 8.4%. This study provides a data reference for the (E) measurement using the neutron TOF method.
Cf rotation method with a water Cherenkov neutron detector田辺 鴻典*; 米田 政夫; 藤 暢輔; 北村 康則*; 三澤 毅*; 土屋 兼一*; 相楽 洋*
Scientific Reports (Internet), 14, p.18828_1 - 18828_10, 2024/08
被引用回数：0 パーセンタイル：0.00(Multidisciplinary Sciences)The global challenge of on-site detection of highly enriched uranium (HEU), a substance with considerable potential for unauthorized use in nuclear security, is a critical concern. Traditional passive nondestructive assay (NDA) techniques, such as gamma-ray spectroscopy with high-purity germanium detectors, face significant challenges in detecting HEU when it is shielded by heavy metals. Addressing this critical security need, we introduce an on-site detection method for lead-shielded HEU employing a transportable NDA system that utilizes the Cf rotation method with a water Cherenkov neutron detector. This cost-effective NDA system is capable of detecting 4.17 g of U within a 12 min measurement period using a Cf source of 3.7 MBq. Integrating this system into border control measures can enhance the prevention of HEU proliferation significantly and offer robust deterrence against nuclear terrorism.
I and 
I using the NaI(Tl) spectrometer of the ANNRI beamline at J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 藤 暢輔; 瀬川 麻里子; 前田 亮; 片渕 竜也*
European Physical Journal A, 60(5), p.120_1 - 120_14, 2024/05
被引用回数：2 パーセンタイル：36.86(Physics, Nuclear)The neutron capture cross section of I and I were measured from the thermal to the keV energy region with the NaI(Tl) spectrometer of the Accurate Neutron-Nucleus Reaction Measurement Instrument beamline in the Materials and Life Science Experimental Facility of the Japan Proton Accelerator Research Complex. The neutron capture yield was determined by means of the total energy detection principle with the pulse-height weighting technique. The present cross section results for I were normalized using the saturated resonance method with a thick-enough 
Au and provide good agreement with JENDL-5 from thermal to about 500 keV. A resonance analysis with the REFIT code was performed and the resonance parameters for I below 310 eV are presented in this work. In the case of I, the three largest resonances of I were employed for the cross section normalization. The present results for I are the first experimental data for the neutron region between thermal and 20 eV. The present data display a different energy dependence than that in the JENDL-5 and JEFF-3.3 and much similar to that in ENDF/B-VIII.0. Notwithstanding, good agreement was found at the thermal region between the present measurement of 31.6 1.3 b and both evaluated and most experimental data.
Ta遠藤 駿典; 木村 敦; 中村 詔司; 岩本 修; 岩本 信之; Rovira Leveroni, G.; 藤 暢輔; 瀬川 麻里子; 前田 亮
Nuclear Science and Engineering, 198(4), p.786 - 803, 2024/04
被引用回数：1 パーセンタイル：17.94(Nuclear Science & Technology)The neutron transmission ratio and capture yield for Ta were measured in J-PARC MLF ANNRI to improve the accuracy of resonance parameters. The total cross section was determined from the transmission ratio in the energy range from 0.2 to 150 eV. The capture cross section was obtained from the capture yield using the pulse height weighting technique (PHWT) in the energy range from thermal to 150 eV. The obtained transmission ratio and capture cross-section were fitted by the resonance analysis code, REFIT, and the resonance parameters were determined below 150 eV. It was also discussed the correlations caused by fitting based on statistical uncertainty and correlations for systematic uncertainty based on sample thickness in the transmission measurements.
I and I using ANNRI at MLF/J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 藤 暢輔; 瀬川 麻里子; 前田 亮; 片渕 竜也*
JAEA-Conf 2023-001, p.74 - 79, 2024/02
Measurements to measure the neutron capture cross section of I and I were performed in the Accurate Neutron Nucleus Reaction Measurement Instrument (ANNRI) at the Materials and Life Science Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). The time-of-flight (TOF) methodology was employed to determine the neutron capture cross section from thermal to about 100 keV. The results from I were used to normalize the I cross section. Preliminary results of a resonance analysis below 100 eV for I are also presented.
土屋 晴文; 藤 暢輔; 大図 章; 古高 和禎; 北谷 文人; 前田 亮; 米田 政夫
Journal of Nuclear Science and Technology, 60(11), p.1301 - 1312, 2023/11
被引用回数：4 パーセンタイル：71.25(Nuclear Science & Technology)An integrated active neutron non-destructive analysis (NDA) system, Active-N, was developed to gain knowledge of active neutron NDA techniques that are applicable to measurements of nuclear materials in highly radioactive nuclear fuels. Active-N, equipped with a D-T neutron generator, combines three complementary active neutron NDA techniques: Differential Die-away Analysis (DDA), Prompt Gamma-ray Analysis (PGA), and Neutron Resonance Transmission Analysis (NRTA). In this paper, we provide an overview of Active-N and then demonstrate that the compact NRTA system in Active-N can quantify nuclear materials. Monte Carlo simulations were conducted to determine the design of the compact NRTA system including a moderator, flight tubes, and a detector shield. To investigate how accurately the compact NRTA system determines areal densities in a sample, measurements were performed with a Pu pellet-type sample as well as metallic plate samples of In and Ag. The experimental areal densities of 
Pu, 
In and 
Ag were consistent with those calculated for the individual nuclei. These results show that it is feasible to develop a compact NRTA system capable of determining the contents of nuclear materials in nuclear fuels. This research was implemented under the subsidy for nuclear security promotion of MEXT.
古高 和禎; 大図 章; 藤 暢輔
Nuclear Engineering and Technology, 55(11), p.4002 - 4018, 2023/11
被引用回数：3 パーセンタイル：62.70(Nuclear Science & Technology)An integrated neutron interrogation system has been developed for non-destructive assay of highly radioactive special nuclear materials, to accumulate knowledge of the method through developing and using it. The system combines a differential die-away (DDA) measurement system for the quantification of nuclear materials and a prompt gamma-ray analysis (PGA) system for the detection of neutron poisons which disturb the DDA measurements; a common D-T neutron generator is used. A special care has been taken for the selection of materials to reduce the background gamma rays produced by the interrogation neutrons. A series of measurements were performed to test the basic performance of the system. The results show that the DDA system can quantify plutonium of as small as 20~mg and it is not affected by intense neutron background up to 4.2~TBq and gamma ray of 2.2~TBq. As a result of the designing of the combined system as a whole, the gamma-ray background counting rate at the PGA detector was reduced down to 
s
even with the use of the D-T neutron generator. The test measurements show that the PGA system is capable of detecting less than 1~g of boron compound and about 100~g of gadolinium compound in~30 min. This research was implemented under the subsidy for nuclear security promotion of MEXT.
Pb and 
Bi in proton-induced reactions near 100 MeV岩元 大樹; 明午 伸一郎; 佐藤 大樹; 岩元 洋介; 石 禎浩*; 上杉 智教*; 八島 浩*; 西尾 勝久; 杉原 健太*; 
elik, Y.*; et al.
Nuclear Instruments and Methods in Physics Research B, 544, p.165107_1 - 165107_15, 2023/11
被引用回数：4 パーセンタイル：62.70(Instruments & Instrumentation)入射陽子エネルギー200MeV以下の中性子生成に関する二重微分断面積(DDX)データの不足は、加速器駆動核破砕システム(ADS)の研究開発などの技術応用における核破砕モデルの検証を妨げている。本研究では、このエネルギー領域におけるADS核破砕ターゲット材料のDDX実験データを取得し、解析予測との比較を通じて核破砕モデルに関する課題を明らかにすることを目的とした。実験は、京都大学のFFAG加速器を用いて行った。100MeV領域のPbとBiの陽子入射核反応に対するDDXを飛行時間法を用いて30から150の角度範囲で測定した。得られたDDXをモンテカルロ法に基づく種々の核破砕モデル及び評価済み核データライブラリによる計算結果と比較した。DDXの測定値と核破砕モデル及び評価済み核データライブラリに基づく解析値を比較した結果、CEM03.03モデルが実験値に最も近い一致を示した。さらに、100MeV領域における陽子入射中性子生成DDXの再現性向上のために対処すべき複数の課題を明らかにした。
前田 亮; 瀬川 麻里子; 藤 暢輔; 遠藤 駿典; 中村 詔司; 木村 敦
Journal of Radioanalytical and Nuclear Chemistry, 332(8), p.2995 - 2999, 2023/08
被引用回数：0 パーセンタイル：0.00(Chemistry, Analytical)The accuracy of the prompt 
-ray analysis is known to degrade for the samples containing neutron-scattering materials, such as hydrogen, depending on its content. Recently, we discovered that the density of the scattering materials also affects the accuracy. In this paper, we developed a correction method for the effect of the sample densities. The developed correction method is straightforward and applicable to samples with unknown densities. The simulation and experiments verified the performance of the correction method. The results confirmed that the correction method could reduce the uncertainty due to sample density from 47% to approximately 1%.
渡辺 幸信*; 定松 大樹*; 荒木 祥平; 中野 敬太; 川瀬 頌一郎*; 金 政浩*; 岩元 洋介; 佐藤 大樹; 萩原 雅之*; 八島 浩*; et al.
EPJ Web of Conferences, 284, p.01041_1 - 01041_4, 2023/05
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)医療用RIの製造や核融合材料の照射損傷、放射性廃棄物の核変換などの研究において重陽子加速器を用いた高強度中性子源が提案されている。そのような中性子源の設計には重陽子を様々な標的に照射した際の中性子生成データが必要である。しかし、重陽子入射中性子生成二重微分断面積などの実験データは十分でない。そこで本研究では、大阪大学核物理研究センター(RCNP)において幅広い原子番号の標的に対する200MeV重陽子入射中性子生成二重微分断面積の系統的な測定を実施した。200MeVの重陽子ビームをビームスウィンガーマグネット内の薄い標的に照射し、放出される中性子を大きさの異なるEJ301検出器(直径及び厚さが2inchと5inch)を7m、20mの位置にそれぞれ設置し、測定した。測定角度は0度から25度までの5角度とし、中性子エネルギーは飛行時間法で決定した。それぞれの測定データは入射エネルギーの半分あたりに特徴的な幅広なピークを示しており、ピークの収量は標的の質量数に従って単調に増加した。DEURACSとPHITSを用いた理論モデル計算との比較の結果、DEURACSの計算結果はPHITSのものよりも実験値に対してより良い一致を示した。加えて、得られたLi, Be, Cの結果を用いてJENDL/DEU-2020とTENDL-2017の核データライブラリのベンチマークを行った。
岩元 大樹; 中野 敬太; 明午 伸一郎; 佐藤 大樹; 岩元 洋介; 杉原 健太*; 西尾 勝久; 石 禎浩*; 上杉 智教*; 栗山 靖敏*; et al.
EPJ Web of Conferences, 284, p.01023_1 - 01023_4, 2023/05
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)加速器駆動システム(ADS)の核特性予測精度の向上と京都大学臨界集合体実験装置(KUCA)におけるADS炉物理実験で用いる中性子源情報の取得を目的として、京都大学の固定磁場強集束(FFAG)加速器を用いた核データ測定実験プログラムを開始した。このプログラムの一環として、鉄,鉛及びビスマスに対する陽子入射二重微分中性子収量(TTNY)及び断面積(DDX)を測定した。測定では、真空チェンバ内に設置された標的試料に107MeVの陽子ビームを照射し、核反応によって標的から発生した粒子の信号を、小型の中性子検出器を用いて検出した。検出信号とFFAGキッカー電磁石の信号の時間差から飛行時間(TOF)を求め、ガンマ線の事象を波形弁別法によって除去して中性子事象をカウントすることで中性子のTOFスペクトルを求めた。得られた中性子のTOFスペクトルから、相対論的運動学によりTTNY及びDDXを求めた。実験で得られたTTNY及びDDXを、モンテカルロ輸送計算コードPHITSによる計算と比較し、PHITSに組み込まれた核反応モデル及び評価済み核データライブラリJENDL-4.0/HEの妥当性を検証するとともに、PHITSによる計算の予測精度を評価した。
岩元 大樹; 中野 敬太; 明午 伸一郎; 佐藤 大樹; 岩元 洋介; 杉原 健太; 西尾 勝久; 石 禎浩*; 上杉 智教*; 栗山 靖敏*; et al.
Journal of Nuclear Science and Technology, 60(4), p.435 - 449, 2023/04
被引用回数：4 パーセンタイル：47.14(Nuclear Science & Technology)加速器駆動核変換システム(ADS)の研究開発及び京都大学臨界実験装置(KUCA)におけるADS未臨界炉物理の基礎研究を目的として、固定磁場強収束(FFAG)加速器を用いて107MeV陽子による鉄、鉛及びビスマス標的に対する二重微分中性子収量(TTNY)を測定した。TTNYは8個の中性子検出器(各検出器は小型のNE213液体有機シンチレータと光電子増倍管より構成される)からなる中性子検出器システムを用いて飛行時間法により得られたものである。測定で得られたTTNYを、粒子・重イオン輸送コードシステム(PHITS)に組み込まれたモンテカルロ法に基づく核破砕反応モデル(INCL4.6/GEM, Bertini/GEM, JQMD/GEM, JQMD/SMM/GEM)及び評価済み高エネルギー核データライブラリ(JENDL-4.0/HE)による計算結果と比較した。JENDL-4.0/HEを含む比較対象のモデルは、検出器角度5度における高エネルギーピークを再現しないなどの特徴的な不一致が見られた。測定で得られたTTNYとPHITSによって評価した20MeV以下のエネルギー及び角度積分中性子収率を比較した結果、INCL4.6/GEMがKUCAにおけるADS炉物理実験のモンテカルロ輸送シミュレーションに適していることが示された。
-ray analysis木下 哲一*; 能任 琢真*; 中島 均*; 小迫 和明*; 加藤 雄大*; 黒岩 洋一*; 倉部 美彩子*; 佐々木 勇気*; 鳥居 和敬*; 前田 亮; et al.
Journal of Radioanalytical and Nuclear Chemistry, 332(2), p.479 - 486, 2023/02
被引用回数：2 パーセンタイル：36.10(Chemistry, Analytical)There are some different chemical and physical forms of water molecules in concretes. Especially, bound water is difficult to determine. In the present work, we determined free + adsorbed water and bound water contained in aggregates and cement pastes, which are component of concretes, by means of conventional gravimetric analysis and prompt -ray analysis (PGA), respectively, in order to evaluate a total water content in concretes. In the PGA, background reduction was attempted by using the time-of-flight (TOF) signal. In addition, the degree of contribution to analytical values by scattered neutrons by samples was evaluated because water would adsorb on the surface of instruments inside the irradiation chamber for the PGA. Contents of the free + adsorbed water and bound water in some geochemical references determined in the present work were compared with the nominal values to confirm the precision. Each water content in aggregates collected from different quarries and cement pastes with different water-to-cement ratios were analyzed. A total water content in young concrete was evaluated on the basis of the analytical values.
岩元 大樹; 明午 伸一郎; 中野 敬太*; 佐藤 大樹; 岩元 洋介; 杉原 健太*; 石 禎浩*; 上杉 智教*; 栗山 靖敏*; 八島 浩*; et al.
Proceedings of 19th Annual Meeting of Particle Accelerator Society of Japan (インターネット), p.404 - 409, 2023/01
加速器駆動核変換システム(ADS)の研究開発に資するため、固定磁場強収束(FFAG)加速器を用い、核データを取得する実験的研究プログラムを開始した。ADSの核設計及び京都大学臨界集合体実験装置(KUCA)における未臨界実験体系の解析で重要となる、鉛及びビスマスの陽子入射中性子収量及び核分裂に関する核データを対象とした。中性子の飛行時間(TOF)測定で要求される短パルスビームの技術開発を行い、その要求値となるビーム幅10ns以下を達成するとともに、107MeV陽子入射による厚い標的中性子収量TTNY及び中性子生成二重微分断面積DDXをTOF法により測定した。TTNY及びDDXの測定には、小型シンチレータと光電子増倍管から構成される中性子検出器を用いた。測定で得られた結果をADSの核設計で用いられるPHITSによる解析値と比較した。さらに、マイクロチャンネルプレート(MCP)と多芯線比例計数管(MWPC)を組み合わせにより、107MeV陽子入射の
Pb核分裂反応から生成される核分裂片の質量数分布を測定した。本プログラムの最終年度となる令和4年度は、Biに対する核分裂片の質量数分布と核分裂で生じる核分裂中性子の測定を実施するとともに、
Np核分裂計数管を用いて、陽子と標的との核反応で形成される中性子場の測定を実施する予定である。
岩元 大樹; 中野 敬太; 明午 伸一郎; 佐藤 大樹; 岩元 洋介; 石 禎浩*; 上杉 智教*; 栗山 靖敏*; 八島 浩*; 西尾 勝久; et al.
JAEA-Conf 2022-001, p.129 - 133, 2022/11
加速器駆動システム(ADS)の核特性予測精度の向上と京都大学臨界集合体実験装置(KUCA)におけるADS炉物理実験で用いる中性子源情報の取得を目的として、京都大学の固定磁場強集束(FFAG)加速器を用いた核データ測定実験プログラムを開始した。このプログラムの一環として、鉄に対する陽子入射二重微分中性子収量(TTNY)及び断面積(DDX)を測定した。測定では、真空チェンバ内に設置された鉄標的に107MeVの陽子ビームを照射し、核反応によって標的から発生した粒子の信号を、小型の中性子検出器を用いて検出した。検出信号とFFAGキッカー電磁石の信号の時間差から飛行時間(TOF)を求め、ガンマ線の事象を波形弁別法によって除去して中性子事象をカウントすることで中性子のTOFスペクトルを求めた。得られた中性子のTOFスペクトルから、相対論的運動学により鉄標的に対するTTNY及びDDXを求めた。
