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Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*
Annals of Nuclear Energy, 225, p.111688_1 - 111688_18, 2026/01
The neutron total and capture cross sections of 
Er were measured at the Accurate Neutron-Nucleus Reaction Measurement Instrument beamline in the Materials and Life Science Experimental Facility of the Japan Proton Accelerator Research Complex. For the neutron total cross-section measurements, Li-glass detectors were employed to derive the neutron transmission ratio of three Er transmission samples with thicknesses of 1 mm, 0.175 mm and 0.05 mm. The neutron capture cross-section was determined from measurements of 0.025-mm-thick Er samples with NaI(Tl) and Ge spectrometers in separate experiments, since they offer complementary capabilities. Moreover, the capture cross-section of 
Er was derived below 1 eV, since it accounted for over 95% of the capture events in Er. Finally, the resolved resonance region up to 65 eV was analyzed using the REFIT code. The resonance parameters of 20 Er resonances, together with one resonance for each 
Er and 
Er were determined in a least-square fit using a combination of both capture data and the transmission data from the thicker 1 mm and 0.175 mm samples. T
中村 龍也; 藤 健太郎; 鬼柳 亮嗣; 大原 高志; 細谷 孝明; 戸邊 雅弘; 菱沼 行男*; 海老根 守澄; 坂佐井 馨
Journal of Physics; Conference Series, 3130(1), p.012002_1 - 012002_6, 2025/11
J-PARC物質・生命科学実験施設に設置されたSENJU中性子回折計用の2次元シンチレータ中性子検出器の高度化を進めている。高度化計画には、薄型、高効率型、真空槽下およびバンク設置用の大面積検出器が含まれる。これはすべて
Li:ZnSと波長シフトファイバーを用いた検出器である。大面積検出器についてはこれまでにオリジナル検出器の2
2倍の有感面積(512512mm)をもつ検出器を開発してきたが、近年ではさらに大面積で長方形の有感面積である検出器を開発している(13倍(256768mm)、23倍(512768mm))。発表ではこれらの検出器の設計やプロトタイプ検出器の実験結果を報告する。
櫻井 惇也*; 鳥形 啓輔*; 松永 学*; 高梨 直人*; 日比野 真也*; 木津 健一*; 森田 聡*; 井元 雅弘*; 下畠 伸朗*; 豊田 晃大; et al.
鉄と鋼, 111(5), p.246 - 262, 2025/04
Creep testing is time-consuming and costly, leading institutions to limit the number of tests conducted to the minimum necessary for their specific objectives. By pooling data from each institution, it is anticipated that predictive models can be developed for a wide range of materials, including welded joints and degraded materials exposed to service conditions. However, the data obtained by each institution is often highly confidential, making it challenging to share with others. Federated learning, a type of privacy-preserving computation technology, allows for learning while keeping data confidential. Utilizing this approach, it is possible to develop creep life prediction models by leveraging data from various institutions. In this paper, we constructed global deep neural network models for predicting creep rupture life of heat-resistant ferritic steels in collaboration with eight institutions using the federated learning system we developed for this purpose. Each institution built a local model using only its own data for comparison. While these local models demonstrated good predictive accuracy for their respective datasets, their predictive performance declined when applied to data from other institutions. In contrast, the global model constructed using federated learning showed reasonably good predictive performance across all institutions. The distance between each institution's data was defined in the space of explanatory variables, with the NIMS data, which had the largest dataset, serving as the reference point. The global model maintained high predictive accuracy regardless of the distance from the NIMS data, whereas the predictive accuracy of the NIMS local model significantly decreased as the distance increased.
I neutron capture cross-section in the keV neutron regionRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*
Journal of Nuclear Science and Technology, 12 Pages, 2025/00
被引用回数：0 パーセンタイル：0.00The I neutron capture cross-section was measured at the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). To obtain accurate results in the keV neutron region, the recently developed neutron filtering technique was employed with a 20-cm-thick Si filter to tailor the incident neutron flux into quasi-monoenergetic neutron peaks with averaged neutron energies of 51.5 and 127.7 keV and, at the same time, hugely increase the signal-to-noise ratio. The present cross-section results were determined form the capture yield ratio of I to that of 
Au and using the evaluated nuclear data from JENDL-5 as reference. The I neutron capture cross section was found to be 0.278 
0.034 b at 51.5 keV and 0.141 0.015 b 127.7 keV, validating the JENDL-5 and JEFF-3.3 evaluations, as well as the results from Noguere et al., in contrast to the larger evaluations of JENDL-4.0 and ENDF/B-VIII.1 and the data from Macklin et al.
Er at ANNRIRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*
JAEA-Conf 2024-002, p.127 - 132, 2024/11
Measurements to measure the total and neutron capture cross section of Er 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). In this study, the preliminary results for the Er neutron total and capture cross sections measured with Li-glass, Ge and NaI(Tl) detectors are presented and compared.
中島 多朗*; 齋藤 開*; 小林 尚暉*; 川崎 卓郎; 中村 龍也; 古川 はづき*; 浅井 晋一郎*; 益田 隆嗣*
Journal of the Physical Society of Japan, 93(9), p.091002_1 - 091002_5, 2024/09
被引用回数：2 パーセンタイル：44.93(Physics, Multidisciplinary)Neutron scattering is a powerful tool to study magnetic structures and cross-correlated phenomena originated from symmetry of the magnetic structures in matter. Among a number of neutron scattering techniques, polarized neutron scattering is quite sensitive to the orientations of the magnetic moments, which are essential to understand microscopic mechanisms of the spin-driven emergent phenomena. Here, we present POlarized Neutron Triple-Axis spectrometer PONTA in the Japan Research Reactor 3 (JRR-3), and show the present capabilities of polarized and unpolarized neutron scattering by introducing recent results from the instrument.
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：54.52(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.
Am neutron capture cross section measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARCRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*
Journal of Nuclear Science and Technology, 61(4), p.459 - 477, 2024/04
被引用回数：2 パーセンタイル：33.46(Nuclear Science & Technology)The neutron capture cross-section of Am was measured from 10 meV to about 1 MeV using the NaI(Tl) spectrometer of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). The total energy detection principle was applied in conjunction with the pulse-height weighting technique to derive the neutron capture yield. The present cross-section results were normalized using a Au sample measurement by applying the saturated resonance method. The thermal cross section was measured to be 708 22 b, in agreement within uncertainties to the present evaluation in JENDL-5 of 709 b. Moreover, the results of a shape resonance analysis of the resolved resonance region are also provided in the present dissertation.
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.
Gd and 
Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC
MLFANNRI木村 敦; 中村 詔司; 遠藤 駿典; Rovira Leveroni, G.; 岩本 修; 岩本 信之; 原田 秀郎; 片渕 竜也*; 寺田 和司*; 堀 順一*; et al.
Journal of Nuclear Science and Technology, 60(6), p.678 - 696, 2023/06
被引用回数：3 パーセンタイル：45.16(Nuclear Science & Technology)Neutron total and capture cross-section measurements of Gd and Gd were performed in the ANNRI at the MLF of the J-PARC. The neutron total cross sections were determined in the energy region from 5 to 100 meV. At the thermal neutron energy, the total cross sections were obtained to be 59.41.7 and 251.94.6 kilobarn for Gd and Gd, respectively. The neutron capture cross sections were determined in the energy region from 3.5 to 100 meV with an innovative method by taking the ratio of the detected capture event rate between thin and thick samples. At the thermal energy, the capture cross sections were obtained as 59.02.5 and 247.43.9 kilobarn for Gd and Gd, respectively. The present total and capture cross sections agree well within the standard deviations. The results for Gd were found to be consistent with the values in JENDL-4.0 and the experimental data given by Mastromarco et al. and Leinweber et al. within one standard deviation. Moreover, the present results for Gd agreed with the evaluated data in JENDL-4.0 and the experimental data by M
ller et al. within one standard deviation and agreed with the data by Mastromarco et al. within 1.4 standard deviations. However, they disagree (11% larger) with the experimental result by Leinweber et al.
Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 堀 順一*; et al.
EPJ Web of Conferences, 284, p.06007_1 - 06007_4, 2023/05
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)A neutron filtering system has been installed at the ANNRI beamline in order to bypass the doublet structure of the incident neutron beam in the keV region. Thick cylindrical slabs of Fe, Si and Cr which share the characteristic of a sharp minimum in the neutron total cross section, were separately introduced in an intermediate stage of the beamline, before the NaI(Tl) spectrometer experimental area. The filtered neutron beams were analyzed by means of both neutron capture and transmission experiments. Moreover, further information about the neutron energy distribution within the filtered peaks was derived through the use of Monte-Carlo simulations with the PHITS code. The characteristics of the filtered neutron beams for Fe, i and Cr are presented together with Au standard experimental results to assess the performance of the neutron filtering system in neutron capture cross section experiments.
Pd using ANNRI at MLF/J-PARC中野 秀仁*; 片渕 竜也*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典; Rovira Leveroni, G.; 児玉 有*
EPJ Web of Conferences, 284, p.01032_1 - 01032_3, 2023/05
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)In the present work, the neutron capture cross section measurements were carried out using 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). A high intensity pulsed neutron beam from Japan Spallation Neutron Source at the MLF using the 3 GeV proton beam was utilized. NaI(Tl) detectors of ANNRI were used for capture measurements. The time-of-flight (TOF) method was employed to determine the incident neutron energy. Two-dimensional data, TOF and pulse-height (PH), were acquired and the data were analyzed based on a PH weighting technique. Resonance parameters were derived from resonance analysis using the REFIT code.
児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 中野 秀仁*; 佐藤 八起*; 堀 順一*; 芝原 雄司*; et al.
EPJ Web of Conferences, 284, p.01024_1 - 01024_3, 2023/05
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)The measurements were performed using the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline at the Japan Proton Accelerator Research Complex (J-PARC). An intense pulsed neutron beam was produced via spallation reaction in the mercury target of the Material and Life Science Experimental Facility by the 3-GeV proton beam of the J-PARC facility. A Time of Flight (TOF) method using a NaI(Tl) detector was employed in this measurements and a pulse-height weighting technique was used to derive a neutron capture yield. A sample of Am-243 with a mass of 38.14 mg (281.8 MBq) was used for the measurements. The neutron energy spectrum was obtained by using the 478 keV gamma-rays from the 
B(n,
)
Li reaction with a boron sample. A preliminary value for the capture cross section of Am-243 will be presented in the contribution.
Am neutron capture cross section in the keV region using Si and Fe-filtered neutron beamsRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*
Journal of Nuclear Science and Technology, 60(5), p.489 - 499, 2023/05
被引用回数：4 パーセンタイル：45.16(Nuclear Science & Technology)The neutron capture cross-section of Am was measured in the keV neutron range using the recently implemented neutron filtering system of the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Materials and Life Science (MLF) facility of the Japan Proton Accelerator Research Complex (J-PARC). Filter arrays consisting of 20 cm of Fe and Si were employed in separate measurements to provide filtered neutron beams with averaged neutron energies of 23.5 (Fe), 51.5 and 127.7 (Si) keV. The present Am results were obtained relative to the Au neutron capture yield by applying the total energy detection principle together with the pulse-height weighting technique. The Am neutron capture cross section was determined as 2.72 0.29 b at 23.5 keV, 2.14 0.26 b at 51.5 keV and 1.32 0.10 b at 127.7 keV with total uncertainties in the range of 8 to 12
, much lower in comparison to the latest time-of-flight experimental data available.
片渕 竜也*; 岩本 修; 堀 順一*; 木村 敦; 岩本 信之; 中村 詔司; Rovira Leveroni, G.; 遠藤 駿典; 芝原 雄司*; 寺田 和司*; et al.
EPJ Web of Conferences, 281, p.00014_1 - 00014_4, 2023/03
Long-lived minor actinides (MA) in nuclear waste from nuclear power plants are a long-standing issue to continue nuclear energy production. To solve the issue, researchers have suggested nuclear transmutation, in which long-lived radionuclides are transmuted into stable or shorter-life nuclides via neutron-induced nuclear reactions. Development of nuclear transmutation systems as an accelerator-driven system requires accurate neutron nuclear reaction data. The present research project entitled "Study on accuracy improvement of fast-neutron capture reaction data of long-lived MAs for development of nuclear transmutation systems" have been conducted as a joint collaboration, including Tokyo Tech, Japan Atomic Energy Agency and Kyoto University. This project focuses on the neutron capture reaction of MAs, especially 
Np, Am and 
Am, in the fast neutron energy region. The final goal of this project is to improve the accuracies of the neutron capture cross sections of Np, Am and Am employing a high-intensity neutron beam from a spallation source of the Japan Proton Accelerator Research Complex (J-PARC) that reduces uncertainties of measurement. To achieve the goal, a neutron beam filter system in J-PARC, sample characteristic assay, and theoretical reaction model study were developed. In this contribution, the overview and results of the project will be presented.
中野 秀仁*; 片渕 竜也*; Rovira Leveroni, G.; 児玉 有*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典
Journal of Nuclear Science and Technology, 59(12), p.1499 - 1506, 2022/12
被引用回数：2 パーセンタイル：23.45(Nuclear Science & Technology)A neutron monitoring detection system was developed for neutron capture cross section measurement using a spallation neutron source. A combination of a plastic scintillator and a thin LiF foil was adopted for the detector. The detector system was tested to study the feasibility of the system. Neutron irradiation experiments were conducted with the Accurate Neutron-Nucleus Reaction Measurement Instrument in the Materials and Life Science facility of the Japan Proton Accelerator Research Complex. A neutron time-of-flight spectrum was successfully measured without significant count loss or detector paralysis. The statistical uncertainty reached 0.7% at neutron energies around 6 meV.
Am neutron capture cross section measurement and resonance analysisRovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 修; 岩本 信之; 片渕 竜也*; 児玉 有*; 中野 秀仁*; 佐藤 八起*
JAEA-Conf 2022-001, p.91 - 96, 2022/11
Neutron capture cross section measurements 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 in a non-filter condition experiment to determine the neutron capture cross section from thermal to about 100 eV. Moreover, experiments were performed using the neutron filtering system to determine the neutron capture cross section at the energy of 23.5 keV using Fe as filter material. In this study, the preliminary results of the Am neutron capture cross section from 10 meV to about 100 eV determined in TOF experiments and at 23.5 keV from Fe filter experiments are presented. In the TOF experiments, the Am neutron capture cross section was normalized by means of the saturated resonance method using a Au sample with a mass of 1.5 g. In addition, for the Fe filter experiments, the capture cross section of Am at the energy of 23.5 keV was determined relative to the Au yield obtained from a measurement using the same Au sample. Moreover, early-stage results of a resonance analysis of the Am capture resonances are also presented.
藤 健太郎; 中村 龍也; 坂佐井 馨; 山岸 秀志*
Proceedings of 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conference (2022 IEEE NSS MIC RTSD) (Internet), 3 Pages, 2022/11
飛行時間法を用いるパルス中性子散乱実験用のリアルタイムデータ表示,保存機器を開発した。開発したモジュールは二次元中性子検出器からの実験データ(二次元イメージ,一次元投影イメージ,TOFスペクトル,カウントデータ等)をリアルタイムで表示することができる。モジュールには標準モードと高速モードの2つの動作モードが備わっている。高速モードではモジュール内の動作を限定することで高速動作を実現しており、大強度の中性子測定においては有用な動作モードである。中性子検出器からの出力信号を模擬したテスト信号を用いて動作試験を行ったところ、通常モード,高速モードでそれぞれ1MHz, 1.6MHzの連続信号を計数損失なしで測定できることを確認した。
中村 龍也; 藤 健太郎; 小泉 智克; 鬼柳 亮嗣; 大原 高志; 海老根 守澄; 坂佐井 馨
Proceedings of 2022 IEEE Nuclear Science Symposium, Medical Imaging Conference and Room Temperature Semiconductor Detector Conference (2022 IEEE NSS MIC RTSD) (Internet), 2 Pages, 2022/11
J-PARC物質・生命科学実験施設に設置されたSENJU回折計用として、新たに薄型の位置敏感シンチレータ中性子検出器を開発した。本検出器は既設のオリジナル検出器と同等の有感面積(256256mm)とピクセル分解能(44mm)を保持しつつ、奥行きは12cm(オリジナルの40%)の薄型へと改良した。製作した6台の検出器はいずれも検出効率60%(2A)、計数均一性5-8%と良好な性能を示した。現在、これらの検出器はビームライン内の回折計に装填されており、数か月の安定動作が確認されている。
先崎 達也; 荒井 陽一; 矢野 公彦; 佐藤 大輔; 多田 康平; 小木 浩通*; 川野邊 崇之*; 大野 真平; 中村 雅弘; 北脇 慎一; et al.
JAEA-Testing 2022-001, 28 Pages, 2022/05
JAEA-Testing-2022-001.pdf:2.33MB
核燃料サイクル工学研究所B棟における試験、分析の実施により発生し、長期間グローブボックス内に保管していた核燃料物質について、当該施設の廃止措置の決定に伴い、高レベル放射性物質研究施設(CPF)の貯蔵庫においてポリ塩化ビニル製の袋(PVCバッグ)で密封して保管していた。CPF安全作業基準に基づく貯蔵物の定期点検においてPVCバッグが徐々に膨らむ状況が確認されたことから、当該試料中から放射線分解によると思われる何らかのガスが発生していると考えられた。ガスが滞留した状態で放置すると、PVCバッグの破裂・破損に繋がるため、ガスが発生しない状態に安定化する必要があると考えた。安定化処理までの処理フローを確立するため、当該核燃料物質の性状を調査した。また、その結果から模擬物質を選定してモックアップ試験を実施した。性状調査においては放射能分析や成分分析、熱分析を実施した。放射性物質濃度及び組成を明らかにするため、
線スペクトロメトリーによる定性分析及び試料溶解による成分分析を実施した。次に、加熱処理による発熱反応を確認するため、酸素をコントロールした条件下で熱分析を実施した。熱分析の結果から有機物含有核燃料物質の組成を推定し、700
Cの熱処理により安定化が可能と判断できたことから、全量を熱処理し安定化処理作業を完了した。核燃料物質の熱処理においては、まずは少量の試料により安全性を確認した後、処理規模をスケールアップした。熱分解処理後の重量減少量の測定により、核燃料物質に混合する有機物が完全に分解できたことを確認した。安定化処理後の核燃料物質はSUS製貯蔵容器に収納してバッグアウトし、CPFの貯蔵庫に貯蔵することで一連の安定化処理作業を完了した。今後の廃止措置においても、性状不明な核燃料物質の安定化処理が必要なケースが想定されることから、安定化処理において得られた知見について報告書にまとめる。
