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青木 健; 清水 厚志; 石井 克典; 守田 圭介; 水田 直紀; 倉林 薫; 安田 貴則; 野口 弘喜; 野本 恭信; 飯垣 和彦; et al.
Annals of Nuclear Energy, 220, p.111503_1 - 111503_7, 2025/09
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)原子力機構は、核熱により水素を製造する原子力水素製造システムの接続技術を確立するため、HTTR-熱利用試験プロジェクトを開始し、その許認可に向けた安全設計及び安全解析を行っている。本研究では、原子力水素製造システムの適用法令及び設計基準の区分の候補の優劣を評価するための相対評価手法を提案し、それをHTTR-熱利用試験施設に適用した。評価の結果、高圧ガス保安法を熱利用試験施設(水素製造施設)に適用し、高圧ガス保安法に基づく設計基準を水蒸気改質器に適用する候補は、いずれの指標においても最下位とならず、最も優れた候補として提案された。
松下 太樹*; 小沢 耀弘*; 荒木 康史; 藤本 純治*; 佐藤 昌利*
Physical Review B, 111(24), p.245131_1 - 245131_11, 2025/06
被引用回数：0We investigate the intrinsic spin Nernst effect (SNE), a transverse spin current induced by temperature gradients, in topological Dirac semimetals (TDSMs) and magnetic Weyl semimetals (MWSMs) with Ising spin-orbit coupling. The intrinsic SNE is described by the spin Berry curvature, which reflects the geometric nature of TDSMs and MWSMs. We clarified that the intrinsic SNE becomes significant when the Fermi energy is near, but slightly deviates from, the energy of the point nodes. In this situation, Bloch electrons with strong spin Berry curvature contribute to the SNE while avoiding carrier compensation between electrons and holes. We found that in TDSMs with small Fermi surfaces, the spin Nernst angle, which measures the efficiency of the SNE, is larger than that observed in heavy metals. This suggests that TDSMs with small Fermi surfaces can achieve efficient heat-to-spin current conversion. In MWSMs, variation in the magnitude of the exchange coupling with magnetic moments significantly changes the SNE, affecting both the direction and magnitude of the spin Nernst current. This implies that ferromagnetic transitions can be used to reverse the spin Nernst current. These results provide the fundamentals for future topological spin caloritronics.
荒井 陽一; 渡部 創; 中原 将海; 船越 智雅; 星野 貴紀; 高畠 容子; 坂本 淳志; 粟飯原 はるか; 長谷川 健太; 吉田 稔生; et al.
Progress in Nuclear Science and Technology (Internet), 7, p.168 - 174, 2025/05
STRADプロジェクトの進捗に係る報告として、CPFホットセルの処理状況とともに、新たなターゲットに係る研究計画と最新のトピックスについて報告する。
Md produced in the 
He + 
Es reaction西尾 勝久; 廣瀬 健太郎; 牧井 宏之; Orlandi, R.; Kean, K. R.*; 塚田 和明; 豊嶋 厚史*; 浅井 雅人; 佐藤 哲也; Chiera, N. M.*; et al.
Physical Review C, 111(4), p.044609_1 - 044609_12, 2025/04
被引用回数：0 パーセンタイル：0.00(Physics, Nuclear)In spontaneous fission (SF) it is found that the mass-asymmetric fission of well-known actinides suddenly changes to the symmetric fission when nucleus has a mass number 
larger than 257. We have measured for the first time fission-fragment mass and total-kinetic-energy (TKE) distributions of the excited compound nucleus Md, populated in the reaction He+Es, using the rare isotope Es with a short half-life, 
=276 days. The fission of Md can be interpreted as involving 3 fission modes: an mass-asymmetric mode and two modes of mass-asymmetric fissions, the latter two are manifested by different TKE values. Predominantly symmetric fission was obtained at the excitation energy of 15.0 MeV. By increasing the energy to 18.0 MeV, the asymmetric fission mode dominates. Both such a strong change of fission modes within a small increase of excitation energy and the enhancement of asymmetric split are new phenomena in fission.
安邊 啓明; 佐藤 活志*
Island Arc, 34(1), p.e70007_1 - e70007_18, 2025/01
被引用回数：1 パーセンタイル：85.45(Geosciences, Multidisciplinary)The Middle Miocene was a period of tectonic transition in the southwest Japan arc. The cessation of backarc spreading at 15 Ma has been thought to have caused a pronounced change in the overall stress state from tension to compression in the arc-perpendicular direction. However, the spatial variation in stress throughout the arc, especially in the forearc, which reflects the characteristics of plate subduction, has yet to be delineated. This study investigates the stress field of the forearc region and its temporal change by applying a stress tensor inversion technique to outcrop-scale dilatant fractures. We measured the attitudes of clastic dikes and mineral veins in the Lower-Middle Miocene Tanabe Group, the paleo-forearc basin deposits in the southwestern Kii Peninsula. Results of paleostress analyses show that the Tanabe Group was influenced by (i) stress with an E-W minimum compressional axis before 15 Ma and (ii) stress with a NW-SE maximum horizontal compressional axis after 15 Ma. In contrast to conventional interpretations, we find that the former stress differed from arc-perpendicular tension in the backarc region before 16 Ma. The latter stress differed from trench-parallel tension on the southernmost Kii Peninsula. Such spatial non-uniformity of the forearc stress can be explained by the occurrence of a dynamic backstop, such as a landward area of the out-of-sequence thrust, beneath the Tanabe Group.
山下 琢磨*; 岩見 聡音*; 光安 優典*; 小野 健太*; 岡 壽崇; 高橋 温*; 木野 康志*; 関根 勉*; 清水 良央*; 千葉 美麗*; et al.
KEK Proceedings 2024-6, p.85 - 90, 2024/12
東京電力・福島第一原子力発電所事故による生物への放射線影響を明らかにするためには、各個体の正確な被ばく線量推定が重要であり、我々は被ばくによって歯中に生成される炭酸ラジカルを測定することで線量推定を行っている。ESR測定で得たスペクトルから炭酸ラジカル由来の成分だけを抽出するため、乱数最適化を用いた多成分解析プログラムを整備した。
岩見 聡音*; 山下 琢磨*; 光安 優典*; 小野 健太*; 岡 壽崇; 高橋 温*; 木野 康志*; 関根 勉*; 清水 良央*; 千葉 美麗*; et al.
KEK Proceedings 2024-6, p.91 - 95, 2024/12
ESR線量計測法の検出限界線量の改善を目指している。本研究では、ESR測定時にマイクロ波出力を変化させ、各ラジカルの飽和挙動を調べた。炭酸ラジカルと有機ラジカルのスピン緩和時間の違いから、マイクロ波出力を4.0mWにすると、S/N比が改善し検出限界線量を引き下げることができるという見込みを得た。
守田 圭介; 青木 健; 清水 厚志; 佐藤 博之
Proceedings of 31st International Conference on Nuclear Engineering (ICONE31) (Internet), 6 Pages, 2024/11
High temperature gas-cooled reactor (HTGR) is expected to use nuclear heat to wide range of industrial applications such as hydrogen production, which is capable of high temperature heat supply with inherent safe characteristics. JAEA started a High Temperature engineering Test Reactor (HTTR) heat application test project to develop coupling technologies between HTGR and a hydrogen production plant necessary to achieve large-scale, carbon-free hydrogen production. One of the key technologies is a safety evaluation method which can simulate an impact of explosion hazards induced in the hydrogen production plant on reactor facility because HTGR hydrogen production system contains large amount of combustible gases such as hydrogen. A computational fluid dynamics code FLACS has been sufficiently validated for dispersion and explosion of combustible gases such as hydrogen and methane worldwide, however, only few attempts have been made for validation of analysis in closed area with small space. A leak of combustible gases to the piping in HTGR hydrogen production system may occur in case of abnormal condition in hydrogen production plant and therefore an explosion in the piping must be considered. This paper describes the validation of FLACS by analyzing explosion experiments in straight piping and complex piping aiming to establish a safety evaluation method for analyzing explosions of combustible gases in piping.
小林 大志*; 佐藤 祐太郎*; 頓名 龍太郎*; 松村 大樹; 佐々木 隆之*; 池田 篤史
Dalton Transactions (Internet), 53(46), p.18616 - 18628, 2024/10
被引用回数：0 パーセンタイル：0.00(Chemistry, Inorganic & Nuclear)This study investigates the dissolution behaviour of zirconium-cerium oxide solid solution ((Zr,Ce)O
/(Ce,Zr)O), which contains a redox-active metal of Ce (Ce(III/IV)) and is of particular importance in nuclear industry. The solid phases of the solid-solution were comprehensively characterised by powder X-ray diffraction (PXRD) with the Rietveld analysis and X-ray absorption spectroscopy (XAS) with factor analysis, indicating that the solid-solution is primarily composed of tetragonal-(Zr,Ce)O and cubic-(Ce,Zr)O. Water immersion of the solid-solution leads to the dissolution of the solid phase at the solid-liquid interface. The addition of a reductant to the system reduces Ce(IV) in the solid-solution to -(III) at the surface, promoting the dissolution of Ce from the solid-solution phase. The release of Ce from the solid-solution also enriches the Zr content in the remaining solid-solution phase at the surface to be more insoluble.
青木 健; 長谷川 武史; 倉林 薫; 野本 恭信; 清水 厚志; 佐藤 博之; 坂場 成昭
Proceedings of 11th International Topical Meeting on High Temperature Reactor Technology (HTR 2024), 6 Pages, 2024/10
原子力機構はHTTR(高温工学試験研究炉)及び水素製造施設を接続するHTTR-熱利用試験を計画している。本研究は、HTTR-熱利用試験施設の安全設計及び安全解析の成果を報告する。安全設計では、期待する安全機能に基づき構築物・系統及び機器の安全重要度分類を定めた。予備安全解析では、RELAP5コードを用いた熱流動解析を行った。予備安全解析は、蒸気発生器の伝熱管破損を除くHTTR-熱利用試験で新たに想定される事象が既設のHTTRの許認可ベース事象に包絡されること、並びに、新たな許認可ベース事象の候補は安全解析の判断基準を満足することを明らかにした。
and 
study of biological effects on cancer cells in the presence of metallic materials during radiotherapy長野 拓也*; 松谷 悠佑; 戒田 篤志*; 野島 瞳*; 古田 琢哉; 佐藤 薫; 吉村 亮一*; 三浦 雅彦*
Journal of Radiation Research (Internet), 65(5), p.628 - 639, 2024/09
被引用回数：0 パーセンタイル：0.00(Biology)X線治療では、正常組織への副作用を最小限に抑えつつ腫瘍を治療するように照射計画が計画される。頭頚部への放射線照射により、歯の金属製の詰め物周辺において重度の粘膜炎(放射線増感作用)が誘発されることがある。しかしながら、この放射線増感メカニズムは不明なままである。本研究では、細胞実験と計算シミュレーションを使用して放射線増感メカニズムを調査した。その結果、細胞実験で観測された増感比は1.2-1.4であり、これは金属近傍の局所線量増加が主要因であることがわかった。一方、臨床前試験としてCT画像に基づく生体内線量評価を実施した結果、人体の複雑な解剖構造により線量増加が過小評価され、微視的な線量評価が必要であることが分かった。本成果は、金属周辺における正常細胞への副反応の正確な理解に貢献するものである。
永塚 健太郎; 野口 弘喜; 長住 達; 野本 恭信; 清水 厚志; 佐藤 博之; 西原 哲夫; 坂場 成昭
Nuclear Engineering and Design, 425, p.113338_1 - 113338_11, 2024/08
被引用回数：4 パーセンタイル：91.70(Nuclear Science & Technology)高温ガス炉は固有の安全性を有し、二酸化炭素を排出することなく大量の水素や高温の熱供給が可能なことから、産業分野の脱炭素化に貢献できる。本報では、原子力機構で進めるHTTR(高温工学試験研究炉)を利用した炉心強制冷却喪失(LOFC)試験等の研究開発成果に加え、現在設計を進めるHTTRを用いた水素製造実証試験(HTTR-熱利用試験)の計画を紹介する。加えて、2030年代後半の運転開始に向け、基本設計が進められている高温ガス炉実証炉計画を紹介する。
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：1 パーセンタイル：23.64(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.
永山 晶大; 原田 寛之; 下川 哲司*; 佐藤 篤*; 山田 逸平; 地村 幹; 小島 邦洸; 山本 風海; 金正 倫計
Proceedings of 20th Annual Meeting of Particle Accelerator Society of Japan (インターネット), p.526 - 530, 2023/11
本研究では、ビームの遅い取り出しのための非破壊型静電セプタムを開発している。従来型と異なり、この装置はビームと衝突しないようにビーム周辺に配置した多段電極で構成されており、発生させた電場によって非破壊でビームを分離する。本研究ではその電場分布を評価すべく、電子銃とビームモニタで構成された試験装置を開発した。その装置に試作電極を設置し、細い電子ビームで電場分布測定の実験を実施した。その測定結果は計算結果との良好な一致を示した。しかし、ビームの分離能力はまだ十分ではない。そこで、電場分布の改良に向けた電極形状や配置の最適化の検討を行った。本発表では、試験装置を用いた電場分布測定実験の結果や改良案を報告する。さらに、本開発の今後の展望についても述べる。
beam at J-PARC RCSSaha, P. K.; 原田 寛之; 米田 仁紀*; 道根 百合奈*; 佐藤 篤*; 柴田 崇統*; 金正 倫計
Proceedings of 20th Annual Meeting of Particle Accelerator Society of Japan (インターネット), p.59 - 63, 2023/11
To overcome the issues and practical limitations associated with the stripper foil used for the charge-exchange injection (CEI) of H beam for high-intensity proton accelerators, we are studying a foil-less H CEI by using only lasers at J-PARC RCS. To establish our principle, we are preparing for a POP (proof-of-principle) demonstration of 400 MeV H stripping to proton by using lasers. We will use both IR and UV lasers in the process of H stripping to protons. A prototype YAG laser system has been developed through experimental studies of 3 MeV H neutralization. We have also developed a multi-reflection laser cavity system to sufficiently reduce the seed laser energy. We have succeeded for 32 reflections to gain on the laser energy up to 16 to obtain a neutralization fraction of 25%. To realize a perfect benefit of the cavity, we also recently developed higher efficient vacuum windows by which we can achieve the laser energy gain to almost 32, proportional to the number of reflections. As a result, the average power of the seed laser can be reduced to 1/32, which is more useful for the UV laser. The laser setup at the 400 MeV beam line is in progress to start POP experimental studies in 2024.
石井 克典; 守田 圭介; 野口 弘喜; 青木 健; 水田 直紀; 長谷川 武史; 永塚 健太郎; 野本 恭信; 清水 厚志; 飯垣 和彦; et al.
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), 4 Pages, 2023/09
JAEA initiated the HTTR heat application test project coupling a hydrogen production facility to the HTTR (high temperature engineering test reactor). The project aims to establish "coupling technologies" between HTGR and hydrogen production achieving large-scale, stable and economically competitive carbon-free hydrogen production using the HTGR heat. Important considerations towards establishment of coupling technologies are development of system technologies for HTGR hydrogen production systems and components required for coupling between two facilities. This paper explains a system concept of the HTTR heat application system which can maintain safe and stable operation of the HTTR against temperature transients induced by abnormal events in a hydrogen production plant with the results of operational scheme as well as heat and mass balance of the system. Development plans for hot gas duct, high temperature isolation valves and helium gas circulators are also presented.
beam at J-PARCSaha, P. K.; 原田 寛之; 米田 仁紀*; 道根 百合奈*; 佐藤 篤*; 柴田 崇統*; 金正 倫計; Johnson, D. E.*
Proceedings of 14th International Particle Accelerator Conference (IPAC 23) (Internet), p.2335 - 2338, 2023/09
We are studying the laser manipulations of H ion beam for single or double neutralization for multi-dimensional applications to utilized in accelerator processes such as stripping, pulse chopping, collimation, extraction, and beam diagnostics for the present and future high-intensity proton accelerators. At J-PARC, a POP (Proof-of-Principle) demonstration 400 MeV H stripping by using only lasers is under preparation. A prototype YAG laser system and a laser cavity system to reduce the laser power has been developed and tested for 3 MeV H neutralization. This allows us established a new generation laser cavity system by recycling/reusing of the seed laser pulse to maximize the interaction efficiency by minimizing pulse energy of the seeder, which can be beneficial for both J-PARC and Fermilab. In addition, we are also developing non-destructive beam diagnostic systems single neutralization at lower H energy, which will be implemented to 400 MeV and can also be easily applicable to Fermilab present Linac including future PIP-II Linac. The 400 MeV H stripping and POP experimental study is expected to start in 2023.
中西 匠*; 堀 優太*; 重田 育照*; 佐藤 寛泰*; 鬼柳 亮嗣; 宗像 孝司*; 大原 高志; 岡澤 厚*; 島田 林太郎*; 坂本 章*; et al.
Journal of the American Chemical Society, 145(35), p.19177 - 19181, 2023/08
被引用回数：5 パーセンタイル：49.39(Chemistry, Multidisciplinary)Multiple proton transfer (PT) controllable by external stimuli plays a crucial role in fundamental chemistry, biological activity, and material science. However, in crystalline systems, controlling multiple PT, which results in a distinct protonation state, remains challenging. In this study, we developed a novel tridentate ligand and iron(II) complex with a short hydrogen bond (HB) that exhibits a PT-coupled spin transition (PCST). Single-crystal X-ray and neutron diffraction measurements revealed that the positions of the two protons in the complex can be controlled by temperature and photoirradiation based on the thermal- and photoinduced PCST. The obtained results suggest that designing molecules that form short HBs is a promising approach for developing multiple PT systems in crystals.
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.
水田 直紀; 守田 圭介; 青木 健; 沖田 将一朗; 石井 克典; 倉林 薫; 安田 貴則; 田中 真人; 井坂 和義; 野口 弘喜; et al.
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 6 Pages, 2023/05
High temperature gas-cooled reactor (HTGR) is expected to extend the use of nuclear heat to a wider spectrum of industrial applications such as hydrogen production, high efficiency power generation, etc., due largely to high temperature heat supply capability as well as inherent safe characteristics. Japan Atomic Energy Agency (JAEA) have been contracted by the Agency for Natural Resources and Energy, part of the Ministry of Economy, Trade and Industry (METI) of Japan, to conduct its Hydrogen Production Demonstration Project Utilizing Very High Temperature. The primary objective of this project is to establish "coupling technology" between HTGR and hydrogen production facility in accordance with "Green Growth Strategy Through Achieving Carbon Neutrality in 2050". From this fiscal year, JAEA initiated a program to produce hydrogen using an HTTR (High Temperature Engineering Test Reactor) to develop coupling technologies between HTGR and hydrogen production facility required for a massive, cost-effective and carbon-free hydrogen production technology. This paper describes the development plan for coupling equipment which is required for an HTTR heat application test as coupling technologies between an HTTR and a hydrogen production facility. The coupling equipment is composed of a high temperature isolation valve to prevent the ingress of the flammable gas and/or the leakage of radioactive materials for nuclear facility, a secondary helium gas circulator to feed a high temperature helium gas, and a high temperature insulation pipe to transport of a high temperature helium gas from an Internal Heat Exchanger (IHX) to a hydrogen production facility. The development plan of coupling equipment contains each target and draft schedule.
