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論文

Eutectic melting and relocation behavior of B$$_{4}$$C pellet-stainless steel under radiative heating

Ahmed, Z.*; Sharma, A. K.*; Pellegrini, M.*; 山野 秀将; 叶野 翔*; 岡本 孝司*

Ceramics International, 50(10), p.17665 - 17680, 2024/05

https://doi.org/10.1016/j.ceramint.2024.02.256

本研究では、2つの独特な破損メカニズムを同定した。一つはB$$_{4}$$Cペレットからステンレス鋼が分離した後に溶融液滴が形成する。もう一つはおそらく熱応力によってB$$_{4}$$Cペレットが複数個に破壊される。可視化技術と界面抵抗解析によって共晶温度を正確に捉えた。

論文

Hydrogenation of silicon-bearing hexagonal close-packed iron and its implications for density deficits in the inner core

森 悠一郎*; 鍵 裕之*; 青木 勝敏*; 高野 将大*; 柿澤 翔*; 佐野 亜沙美; 舟越 賢一*

Earth and Planetary Science Letters, 634, p.118673_1 - 118673_8, 2024/05

https://doi.org/10.1016/j.epsl.2024.118673

水素による鉄の体積膨張に対するケイ素の効果を調べるため、高圧高温下でのhcp-Fe$$_{0.95}$$Si$$_{0.05}$$の中性子回折実験とX線回折実験を行った。中性子回折実験は重水素化hcp-Fe$$_{0.95}$$Si$$_{0.05}$$に対して13.5GPa, 900K及び12.1GPa, 300Kで行い、得られたプロファイルからリートベルト解析を用いて水素占有率を決定した。hcp-Fe-SiのP-V-T状態方程式を組み合わせることにより、hcp-Fe$$_{0.95}$$Si$$_{0.05}$$の水素による体積膨張が純粋なhcp鉄の体積膨張よりも10%大きいことを示した。得られた値を用いて、内核の密度欠損を再現できる水素量を見積もったところ、シリコンの影響がない場合に比べて50%減少した。hcp-Fe$$_{0.95}$$Si$$_{0.05}$$で内核の密度欠損を再現した場合、内核と外核で可能な水素量xはそれぞれ0.07と0.12-0.15と計算された。

論文

ナトリウム-溶融塩熱交換器を有する蓄熱式高速炉の安全設計技術開発; プロジェクト全体概要

山野 秀将; 栗坂 健一; 高野 和也; 菊地 晋; 近藤 俊樹; 梅田 良太; 白倉 翔太*

第27回動力・エネルギー技術シンポジウム講演論文集(インターネット), 5 Pages, 2023/09

溶融塩蓄熱式高速炉の安全設計方針及びリスク評価技術、ナトリウム-溶融塩の熱交換性能評価技術と伝熱向上方策、及びナトリウム-溶融塩の化学反応特性評価と安全性向上方策を開発する研究プロジェクトを進めている。ここでは、プロジェクト全体概要について報告する。

論文

First observation of $$^{28}$$O

近藤 洋介*; Achouri, N. L.*; Al Falou, H.*; Atar, L.*; Aumann, T.*; 馬場 秀忠*; Boretzky, K.*; Caesar, C.*; Calvet, D.*; Chae, H.*; et al.

Nature, 620(7976), p.965 - 970, 2023/08

https://doi.org/10.1038/s41586-023-06352-6
 被引用回数：6 パーセンタイル：93.49(Multidisciplinary Sciences)

非常に中性子が過剰な原子核$$^{28}$$Oは、陽子、中性子ともに魔法数であることから古くからその性質に興味が持たれていたが、酸素の最後の束縛核$$^{24}$$Oよりも中性子が4個も多いため、これまで観測されてこなかった。この論文では、理化学研究所RIBFにて$$^{29}$$Fからの1陽子ノックアウト反応によって$$^{28}$$Oを生成し、そこから放出される中性子を測定することによって初めてその観測に成功した。核構造の観点からは、$$^{28}$$Oでは二重閉殻が保たれているか興味が持たれていたが、実験で得られた分光学的因子が殻模型計算で予言されて程度の大きいことから、閉殻構造をもたない可能性が高いことがわかった。

論文

Intruder configurations in $$^{29}$$Ne at the transition into the island of inversion; Detailed structure study of $$^{28}$$Ne

Wang, H.*; 安田 昌弘*; 近藤 洋介*; 中村 隆司*; Tostevin, J. A.*; 緒方 一介*; 大塚 孝治*; Poves, A.*; 清水 則孝*; 吉田 数貴; et al.

Physics Letters B, 843, p.138038_1 - 138038_9, 2023/08

https://doi.org/10.1016/j.physletb.2023.138038
 被引用回数：2 パーセンタイル：79.22(Astronomy & Astrophysics)

$$^{29}$$Neからの1中性子除去反応を用いて、$$^{28}$$Neの詳細な$$gamma$$線分光を行った。平行運動量分布の解析に基づき、$$^{28}$$Neの準位構造とスピンパリティを決定し、初めて負のパリティ状態を同定した。測定された断面積と運動量分布から、N=20とN=28のシェルギャップの消失の証拠となる有意なintruder p-wave強度が明らかになった。束縛状態については、弱いf-waveの可能性のある強度が観測された。いくつかの有効相互作用を用いた大規模殻模型計算では、実験的に観測された大きなp-wave強度と小さなf-wave強度は再現されず、Ne同位体に沿った反転の島への遷移の完全な理論的記述への挑戦が続いていることを示している。

論文

Neutron production in the interaction of 200-MeV deuterons with Li, Be, C, Al, Cu, Nb, In, Ta, and Au

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

https://doi.org/10.1051/epjconf/202328401041
 被引用回数：0 パーセンタイル：0.21(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。

論文

$$^{241}$$Am neutron capture cross section in the keV region using Si and Fe-filtered neutron beams

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*

Journal of Nuclear Science and Technology, 60(5), p.489 - 499, 2023/05

https://doi.org/10.1080/00223131.2022.2116496
 被引用回数：2 パーセンタイル：48.47(Nuclear Science & Technology)

The neutron capture cross-section of $$^{241}$$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 $$^{nat}$$Fe and $$^{nat}$$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 $$^{241}$$Am results were obtained relative to the $$^{197}$$Au neutron capture yield by applying the total energy detection principle together with the pulse-height weighting technique. The $$^{241}$$Am neutron capture cross section was determined as 2.72 $$pm$$ 0.29 b at 23.5 keV, 2.14 $$pm$$ 0.26 b at 51.5 keV and 1.32 $$pm$$ 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.

論文

Fast-neutron capture cross section data measurement of minor actinides for development of nuclear transmutation systems

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

https://doi.org/10.1051/epjconf/202328100014

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 $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$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 $$^{237}$$Np, $$^{241}$$Am and $$^{243}$$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.

論文

$$^{241}$$Am neutron capture cross section measurement using the NaI(Tl) spectrometer of the ANNRI beamline of J-PARC

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*; 佐藤 八起*

Journal of Nuclear Science and Technology, 19 Pages, 2023/00

https://doi.org/10.1080/00223131.2023.2239885
 被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)

The neutron capture cross-section of $$^{241}$$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 $$^{197}$$Au sample measurement by applying the saturated resonance method. The thermal cross section was measured to be 708 $$pm$$ 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.

論文

Development of safety design technologies for sodium-cooled fast reactor coupled to thermal energy storage system with sodium-molten salt heat exchanger

山野 秀将; 栗坂 健一; 高野 和也; 菊地 晋; 近藤 俊樹; 梅田 良太; 白倉 翔太*; 林 正明*

Proceedings of 8th International Conference on New Energy and Future Energy Systems (NEFES 2023) (Internet), p.27 - 34, 2023/00

https://doi.org/10.3233/ATDE231072
 被引用回数：0 パーセンタイル：0.04(Green & Sustainable Science & Technology)

溶融塩蓄熱式高速炉の安全設計方針及びリスク評価技術、ナトリウム-溶融塩の熱交換性能評価技術と伝熱向上方策、及びナトリウム-溶融塩の化学反応特性評価と安全性向上方策を開発する研究プロジェクトを進めている。ここでは、プロジェクト全体概要について報告する。

論文

Development of a neutron beam monitor with a thin plastic scintillator for nuclear data measurement using spallation neutron source

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

https://doi.org/10.1080/00223131.2022.2067598
 被引用回数：1 パーセンタイル：27.23(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 $$^{6}$$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.

論文

$$^{241}$$Am neutron capture cross section measurement and resonance analysis

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*; 佐藤 八起*

JAEA-Conf 2022-001, p.91 - 96, 2022/11

https://doi.org/10.11484/jaea-conf-2022-001

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 $$^{241}$$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 $$^{241}$$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 $$^{241}$$Am at the energy of 23.5 keV was determined relative to the $$^{197}$$Au yield obtained from a measurement using the same Au sample. Moreover, early-stage results of a resonance analysis of the $$^{241}$$Am capture resonances are also presented.

論文

Sodium-cooled Fast Reactors

大島 宏之; 森下 正樹*; 相澤 康介; 安藤 勝訓; 芦田 貴志; 近澤 佳隆; 堂田 哲広; 江沼 康弘; 江連 俊樹; 深野 義隆; et al.

Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07

https://shop.elsevier.com/books/sodium-cooled-fast-reactors/morishita/978-0-12-824076-2

ナトリウム冷却高速炉(SFR: Sodium-cooled Fast Reactor)の歴史や、利点、課題を踏まえた安全性、設計、運用、メンテナンスなどについて解説する。AIを利用した設計手法など、SFRの実用化に向けた設計や研究開発についても述べる。

論文

KeV-neutron capture cross-section measurement of $$^{197}$$Au with a Cr-filtered neutron beam at the ANNRI beamline of MLF/J-PARC

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*; 佐藤 八起*; et al.

Journal of Nuclear Science and Technology, 59(5), p.647 - 655, 2022/05

https://doi.org/10.1080/00223131.2021.1997666
 被引用回数：1 パーセンタイル：15.09(Nuclear Science & Technology)

Cr-filtered keV-neutron experiments were performed in 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 measure the neutron capture cross-section of $$^{197}$$Au. The energy range of the neutron filtering system at ANNRI was extended through the use of 15 cm of $$^{nat}$$Cr as filter material to tailor quasi-monochromatic neutron peaks with averaged neutron energies of 133.4 and 45.0 keV. The performance of the $$^{nat}$$Cr filter assembly was evaluated by means of experimental capture and transmission analyses, together with the use of Monte-Carlo simulations. The present $$^{197}$$Au neutron capture cross-section results provide agreement within uncertainties with the JENDL-4.0 standard evaluated library and the IAEA standard data library further demonstrating the capabilities of the neutron filtering system at ANNRI.

論文

Neutron filtering system for fast neutron cross-section measurement at ANNRI

Rovira Leveroni, G.; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之; 遠藤 駿典; 片渕 竜也*; 寺田 和司*; 児玉 有*; 中野 秀仁*; et al.

JAEA-Conf 2021-001, p.156 - 161, 2022/03

https://doi.org/10.11484/jaea-conf-2021-001

A neutron filtering system has been designed in order to bypass the double-timed structure of the beam. Filter materials were introduced into the rotary collimator of the ANNRI beamline in order to produce quasi-monoenergetic neutron filtered beams. Filter assemblies consisting of Fe with a thickness of 20 cm, and Si with thicknesses of 20 cm and 30 cm of Si were used separately to produce filtered neutron peaks with energies of 24 keV (Fe) and of 54 and 144 (Si). In this study, the characteristics and performance of the neutron filtering system at ANNRI using Fe and Si determined from both measurements and simulations are presented. The incident neutron flux was tested and analyzed by means of transmission and capture experiments. Moreover, simulations using the PHITS code were performed in order to determine the energy distribution of the integrated filtered peaks and assess the reliability of experimental results. Finally, preliminary results of the capture cross section of $$^{197}$$Au at the filtered energies of 24, 54 and 144 keV are also presented using the NaI(Tl) spectrometer alongside the neutron filtering system.

論文

Development of a neutron beam monitor for nuclear data measurement using spallation neutron source

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

JAEA-Conf 2021-001, p.166 - 170, 2022/03

https://doi.org/10.11484/jaea-conf-2021-001

In neutron capture cross section measurement, monitoring the number of the incident neutrons is necessary. However, in measurement with J-PARC/ANNRI, direct neutron monitoring system has not been employed. Conventional neutron detectors cannot be used as a beam monitor at ANNRI because of two reasons, high counting rate environment and gamma-flash. In general, a semiconductor detector or an inorganic scintillator, which is adopted for a neutron detector, has relatively longer response time and is unsuitable for beam monitoring at ANNRI. Therefore, a combination of a thin plastic scintillator and a $$^{6}$$LiF foil was selected as a detection system, whose fast response enabled detecting neutrons at a high counting rate. Low gamma ray sensitivity of a thin plastic scintillator allows measuring fast TOF region without count loss or detector paralysis. The geometry of the $$^{6}$$LiF foil, the plastic scintillator, and photomultiplier tube (PMT) was designed. The optimal thickness of the $$^{6}$$LiF foil was determined with simulation codes, SRIM and PHITS. The detector system was tested under the high neutron irradiation condition at J-PARC /ANNRI. A neutron TOF spectrum was successfully measured without significant count loss or detector paralysis. A neutron energy spectrum was driven from difference of TOF spectrum with and without $$^{6}$$LiF. The neutron spectrum was compared with a past neutron spectrum and good agreement was obtained. Statistic error was 0.68 $$%$$ at 6.0 meV even though measurement times in this study were short.

論文

A New method to reduce systematic uncertainties of capture cross section measurement using a sample rotation system

児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 中野 秀仁*; 寺田 和司*; 木村 敦; 中村 詔司; 遠藤 駿典

JAEA-Conf 2021-001, p.162 - 165, 2022/03

https://doi.org/10.11484/jaea-conf-2021-001

Precise nuclear data for neutron-induced reactions are necessary for the design of nuclear transmutation systems. Nevertheless, current uncertainties of nuclear data for minor actinide (MA) does not achieve requirements for the design of transmutation facilities. The determination of an incident neutron flux for measurements of neutron capture cross section is one of the main causes that affect the final uncertainty of the cross section results. In the present work, we suggest a new method to reduce systematic uncertainties of capture cross section measurements. The method employs change of the self-shielding effect with sample rotation angle. In capture cross section measurements in ANNRI, a boron sample is placed to determine the incident neutron spectrum by counting 478 keV $$gamma$$-ray from the $$^{10}B(n,alphagamma)^{7}Li$$ reaction. In this method, the boron sample is tilted with respect to the neutron beam direction, thereby changing the effective area. This results in change of the shapes of time-of-flight (TOF) spectrum of 478 keV $$gamma$$-ray from the $$^{10}B(n,alphagamma)^{7}Li$$ reaction with the tilted angle. Comparing the difference of the TOF spectra at different angles and assuming the 1/v energy dependence of cross section of the $$^{10}B(n,alphagamma)^{7}Li$$ reaction, the area density of the boron sample can be determined without using the sample mass and area. Theoretical and experimental studies on the new method are ongoing. Calculation using Monte Carlo simulation code PHITS were carried out to study the feasibility of the present method. Test experiments using a sample rotation system at ANNRI were also performed.

論文

KeV-region analysis of the neutron capture cross-section of $$^{237}$$Np

Rovira Leveroni, G.; 片渕 竜也*; 登坂 健一*; 松浦 翔太*; 児玉 有*; 中野 秀仁*; 岩本 修; 木村 敦; 中村 詔司; 岩本 信之

Journal of Nuclear Science and Technology, 59(1), p.110 - 122, 2022/01

https://doi.org/10.1080/00223131.2021.1954104
 被引用回数：3 パーセンタイル：43.41(Nuclear Science & Technology)

Neutron capture cross-section measurements for $$^{237}$$Np have been conducted with 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) using neutrons with energy ranging from thermal energy to 1 MeV. A Time of Flight (TOF) method using a NaI(Tl) detector was employed for these measurements and the data were analyzed based on the pulse-height weighting technique in order to derive the neutron capture cross-section. The absolute capture cross-section was determined using the whole shape of the first resonance from JENDL-4.0 together with the total neutron flux derived from a $$^{197}$$Au sample measurement in which the first resonance was completely saturated. Both normalization techniques present agreement within 2%. The present results are also compared evaluated data libraries. There is a discrepancy of 10-25% discrepancy from 0.5 to 20 keV with JENDL-4.0. Nonetheless, above this energy, the JENDL-4.0 seems to reproduce the present data better as the results agree within uncertainties up to 500 keV. The cross-section results contain errors below 4% from 0.5 to 30 keV. However, the total uncertainty increases to over 8% over that energy. Along with the cross section measurement, theoretical calculations were performed to reproduce the present results.

論文

Measurements of the neutron capture cross section of $$^{243}$$Am around 23.5 keV

児玉 有*; 片渕 竜也*; Rovira Leveroni, G.; 木村 敦; 中村 詔司; 遠藤 駿典; 岩本 信之; 岩本 修; 堀 順一*; 芝原 雄司*; et al.

Journal of Nuclear Science and Technology, 58(11), p.1159 - 1164, 2021/11

https://doi.org/10.1080/00223131.2021.1943557
 被引用回数：4 パーセンタイル：54.16(Nuclear Science & Technology)

The neutron capture cross section of $$^{243}$$Am was measured with a pulsed neutron beam from a spallation neutron source of the Japan Proton Accelerator Research Complex. A Fe neutron beam filter was used to make the incident neutron beam mono-energetic around 23.5 keV. The neutron capture $$gamma$$-rays were detected with a NaI(Tl) detector. The pulse height weighting technique was employed to derive the neutron capture cross section from the pulse height spectrum. The cross section was determined relative to the capture cross section of $$^{197}$$Au of JENDL-4.0. The neutron capture cross section of $$^{243}$$Am was determined with a smaller uncertainty than previous measurements. The previous measurements and the JENDL-4.0 cross sections were found to be lower than the present result.

論文

Neutron beam filter system for fast neutron cross-section measurement at the ANNRI beamline of MLF/J-PARC

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*; 寺田 和司*; 児玉 有*; 中野 秀仁*; et al.

Nuclear Instruments and Methods in Physics Research A, 1003, p.165318_1 - 165318_10, 2021/07

https://doi.org/10.1016/j.nima.2021.165318
 被引用回数：4 パーセンタイル：54.40(Instruments & Instrumentation)

A neutron filtering system has been introduced in the Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) beamline in the Material and Life Science (MLF) building of the Japan Proton Accelerator Research Complex (J-PARC) in order to produce quasi-monoenergetic neutron beams. The filtered neutron spectrum by the filter assemblies was analyzed by means of capture and transmission measurements and also by Monte Carlo simulations using PHITS. The characteristics of the filtered neutron beam are discussed alongside its viability in future applications for neutron cross-section measurements in the fast neutron region.

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