Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Lee, J.; Rossi, F.; 弘中 浩太; 小泉 光生; 芝 知宙
JAEA-Conf 2026-001, p.44 - 48, 2026/06
The Japan Atomic Energy Agency (JAEA) has been developing various non-destructive assay (NDA) techniques to verify nuclear materials. However, one major challenge in NDA is measuring highly radioactive materials. To address this, neutron resonance analysis (NRA) has been proposed as a promising active neutron NDA technique. NRA combines neutron resonance transmission analysis (NRTA) with neutron resonance capture analysis (NRCA) and the newly introduced neutron resonance fission neutron analysis (NRFNA). In an NRA system, a pulsed neutron beam, in conjunction with the neutron time-of-flight (TOF) method, is used to measure transmitted neutrons, capture gamma-rays, and fission neutrons from a fissile material sample. The system employs a GS20 glass scintillator for detecting transmitted neutrons, while a pulse shape discrimination (PSD) plastic scintillator is used to detect and discriminate between capture gamma-rays and fission neutrons. The positions and depths of resonance peaks or dips in the TOF spectra are determined by the neutron cross sections of nuclides and their amount in the sample. Therefore, to accurately identify and quantify fissile materials based on these spectra, the use of the evaluated nuclear data library is essential. This presentation will provide a detailed overview of the NRA project and discuss the critical role of accurate nuclear data in its success.
Rossi, F.; Lee, J.; 吉見 優希*; 弘中 浩太; 芝 知宙; 寺田 和司*; 堀 順一*
KURNS Progress Report 2025, P. 97, 2026/06
The ISCN of the JAEA is developing a combined neutron resonance analysis (NRA) system aims to identify and quantify fissile material in an unknown sample. Neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA) are used together with the proposed neutron resonance fission neutron analysis (NRFNA). Using a pulsed neutron beam with the neutron time-of-flight (TOF) technique, prompt capture gamma rays and fast fission neutrons from fissile nuclides are measured at the sample location with plastic scintillators able to perform n/g pulse shape discrimination (PSD). In this paper, we report a demonstration experiment for highly enriched uranium samples performed at KURNS-LINAC. This work is supported by MEXT under the subsidy for the "promotion for strengthening nuclear security and the like".
system社本 真一*; 安井 幸夫*; 吉澤 香奈子*; 野田 幸男*; 高橋 美和子*; 大貫 惇睦*; 芳賀 芳範; 石角 元志*; 山内 宏樹; Huang, T.-C.*; et al.
Physical Review B, 113(23), p.235126_1 - 235126_7, 2026/06
被引用回数：0 パーセンタイル：0.00(Materials Science, Multidisciplinary)
-Mn shows a large Sommerfeld constant 
of 70 mJ,
,Mn
,,K
, which is one of the largest values in 3-electron systems. Although the origin has been attributed to the fluctuating magnetic moment, there are no material-dependent systematic studies in the 3-electron systems except for doped -Mn. The ordered -Mn structure compounds Mn
TX (T = Co, Rh, Ir; X = Si, Ge) also exhibit the enhancement. We have studied the enhancement in MnTX system. The enhancement has been often accompanied with magnetic short-range order. The mechanism of the magnetic short-range order is discussed based on the phase diagrams of MnTX system. The phase diagrams are categorized in two groups. One group of MnCoSi and MnRhSi exhibits the magnetic short-range order above the N
el temperature, whereas the others do not. The two groups can be separated by the spin-orbit coupling value, regardless of the cubic lattice parameter.
Gu, G. H.*; Jeong, S. G.*; Lee, J. H.*; Harjo, S.; Gong, W.; Amanov, A.*; Bae, J. W.*; Kwon, H.*; Kim, H. S.*
International Journal of Plasticity, 197, p.104581_1 - 104581_21, 2026/02
被引用回数：6 パーセンタイル：80.21(Engineering, Mechanical)Stacking fault energy (SFE) controls key deformation mechanisms in metals. This study demonstrates that apparent SFE and deformation behavior can be tuned by modifying only the near-surface microstructure (
100 um) through surface severe plastic deformation. The resulting gradient microstructure reduces apparent SFE, promoting martensitic transformation via preferential nucleation and stress partitioning. Consequently, mechanical properties are enhanced, achieving higher strength with minimal ductility loss, highlighting the effectiveness of localized microstructural engineering.
Rossi, F.; Lee, J.; 吉見 優希*; 芝 知宙; 寺田 和司*; 堀 順一*
第46回日本核物質管理学会年次大会会議論文集(インターネット), 4 Pages, 2025/12
The Japan Atomic Energy Agency is developing a non-destructive system to detect fissile nuclear materials within a sample combining resonance analysis from prompt fission neutrons, capture gamma-rays, and transmitted neutrons. The detection setup includes an array of plastic scintillators at the sample and a downstream 
Li scintillator. Recent improvements focus on better neutron/gamma discrimination using advanced EJ-276D plastic scintillators and optimized pulse shape discrimination analysis. Tests were conducted at the Kyoto University time-of-flight facility with natural and enriched uranium samples. This paper presents the latest design updates and experimental results from the system's development. This work is supported by MEXT under the subsidy for the "promotion for strengthening nuclear security and the like".
Rossi, F.; Lee, J.; 吉見 優希*; 弘中 浩太; 小泉 光生; 芝 知宙; 寺田 和司*; 堀 順一*
ESARDA Bulletin, (67), p.59 - 67, 2025/12
ISCN is developing an advanced neutron resonance analysis system for the identification and quantification of fissile materials. This system integrates three complementary techniques: NRTA, NRCA, and NRFNA, enabling simultaneous detection and improving sensitivity for fissile material identification. To evaluate the system's performance, we conducted a series of experiments using natural uranium samples with a thickness from 1.5 to 6.0 mm enclosed in a 2 cm thick box made of lead. The results show that even if the presence of lead generates significant background noise due to neutron scattering and reflection, a clear identification of 
U signatures is possible. These findings highlight the system's versatility and effectiveness in shielding scenarios, offering a promising tool for nuclear security and nonproliferation applications. By enabling concurrent measurements, the system improves accuracy and provides an innovative method for enhancing regulatory and safeguard efforts in the nuclear industry. This work is supported by MEXT under the subsidy for the "promotion for strengthening nuclear security and the like".
/graphene/yttrium iron garnet quadruple heterostructuresChoi, J. W.*; 吉川 貴史; Lee, S.-K.*; 他13名*
Journal of Materials Chemistry A, 13(32), p.26690 - 26699, 2025/08
被引用回数：1 パーセンタイル：23.54(Chemistry, Physical)Strong spin-orbit coupling (SOC) materials and graphene have recently emerged as promising interfacial layers for tailoring spin transport in normal metal/ferromagnet heterostructures. However, spin-to-charge conversion in Pt/two-dimensional (2D) layer/graphene/yttrium iron garnet (YIG) heterostructures remains experimentally unexplored. This study investigates the effects of monolayer graphene and its interfacial coupling with a non-magnetic 2D transition metal dichalcogenide (TMDC) with relatively strong SOC on the longitudinal spin Seebeck effect (LSSE) in Pt/TiSe (or ZrSe)/graphene/YIG quadruple heterostructures. Interfacial SOC between TMDC and graphene is demonstrated to induce an additional spin-to-charge conversion channel in the Pt layer, generating a charge current opposite in direction to the conventional inverse spin Hall effect-induced current from YIG and thereby leading to a net suppression of the LSSE signal. Thus, the study highlights the potential of non-magnetic TMDC interlayers for modulating spin transport, offering new design pathways for spintronic devices.
ders band-assisted high uniform ductility in ultrastrong ferrous medium-entropy alloy via hierarchical microstructureKwon, H.*; Lee, J. H.*; Zargaran, A.*; Harjo, S.; Gong, W.; Wang, J.*; Gu, G. H.*; Lee, B.-J.*; Bae, J. W.*; Kim, H. S.*
International Journal of Plasticity, 190, p.104378_1 - 104378_18, 2025/07
被引用回数：15 パーセンタイル：94.66(Engineering, Mechanical)In this work, we harness a hierarchical microstructure to simultaneously tailor strengthening and deformation mechanisms in a Co
Cr
Fe
Ni
Mo
(at%) ferrous medium-entropy alloy (MEA). A simple thermomechanical process (cold rolling and 90 s annealing) produces ultrafine recrystallized grains, non-recrystallized grains with substructures, and intragranular nanoprecipitates. This structure, with high dislocation density and fine grains, yields a high strength of 1.60 GPa but can risk premature fracture. To overcome this, Lders deformation, enabled by ultrafine grain boundaries and stress-induced martensitic transformation at pre-existing nucleation sites, is employed. Stable Lders band propagation delays strain hardening and enables large uniform ductility. As a result, a tensile strength of 1.84 GPa and uniform elongation of 20% are achieved, matching the best tensile properties among reported multi-principal element alloys.
Kim, M.*; Lee, C.*; 杉田 裕; Kim, J.-S.*; Jeon, M.-K.*
Geomechanics for Energy and the Environment, 41, p.100628_1 - 100628_9, 2025/03
被引用回数：2 パーセンタイル：53.68(Energy & Fuels)この研究では、DECOVALEX-2023プロジェクトの一環として幌延の地下研究施設で実施された実規模大の人工バリア試験の数値解析を使用して、非等温二相流のモデリングに対する主要変数の選択の影響を調査した。検証済みの数値モデルを使用して、人工バリアシステム内の不均質多孔質媒体の熱-水連成挙動を解析した。支配方程式を離散化する際の2つの異なる主要変数スキームを比較したところ、結果に大きな違いがあることが明らかになった。
Lee, J.; Rossi, F.; 児玉 有; 弘中 浩太; 小泉 光生; 佐野 忠史*; 松尾 泰典*; 堀 順一*
Annals of Nuclear Energy, 211, p.111017_1 - 111017_7, 2025/02
被引用回数：1 パーセンタイル：19.36(Nuclear Science & Technology)Silica glass has been used as a base and host material in vitrified radioactive waste and lithium glass scintillator for neutron detection because of its superb transparency, high heat resistance, and excellent chemical inertness. Therefore, an accurate total cross section of the silica glass is important to evaluate the criticality safety for the vitrified wastes and to understand the neutron response for lithium glass scintillators accurately. In the present study, to provide the accurate total cross section in the thermal and epithermal energy range, the neutron transmission measurements were carried out by a pulsed neutron beam with the time-of-flight method at the Kyoto University Institute for Integrated Radiation and Nuclear Science - Linear Accelerator. We obtained the neutron total cross section of the silica glass in the energy region from 0.002 eV to 25 eV. The obtained results were compared and discussed with the previous results and the evaluated data.
小泉 光生; 伊藤 史哲*; Lee, J.; 弘中 浩太; 高橋 時音; 鈴木 敏*; 有川 安信*; 安部 勇輝*; Wei, T.*; 余語 覚文*; et al.
第45回日本核物質管理学会年次大会会議論文集(インターネット), 4 Pages, 2024/11
Neutron resonance transmission analysis (NRTA) is a non-destructive method applicable for measuring nuclear material using a time-of-flight (TOF) technique with a pulsed neutron source. To realize a high resolution compact NRTA system, use of a short-pulsed neutron source is essential. Laser-driven neutron sources (LDNSs) are well-suit for generating such neutron beams due to their short pulse width. The advances in laser technology will further reduce the system's size and improve practicality. In this study, we demonstrate the measurement of a neutron transmission TOF spectrum of a sample containing indium and silver using the LDNS of the Osaka University. The obtained spectrum was analyzed using the least-square nuclear-resonance fitting program, REFIT, showcasing for the first time the potential of an LDNS for nondestructive areal-density material characterization.
小泉 光生; 伊藤 史哲*; Lee, J.; 弘中 浩太; 高橋 時音; 鈴木 敏*; 有川 安信*; 安部 勇輝*; Lan, Z.*; Wei, T.*; et al.
Scientific Reports (Internet), 14, p.21916_1 - 21916_9, 2024/09
被引用回数：5 パーセンタイル：62.62(Multidisciplinary Sciences)Laser-driven neutron sources (LDNSs) can generate strong short-pulse neutron beams, which are valuable for scientific studies and engineering applications. Neutron resonance transmission analysis (NRTA) is a nondestructive technique used for determining the areal density of each nuclide in a material sample using pulsed thermal and epithermal neutrons. Herein, we report the first successful NRTA performed using an LDNS driven by the Laser for Fast Ignition Experiment at the Institute of Laser Engineering, Osaka University. The key challenge was achieving a well-resolved resonance transmission spectrum for material analysis using an LDNS with a limited number of laser shots in the presence of strong background noise. We addressed this by employing a time-gated Li-glass scintillation neutron detector to measure the transmission spectra, reducing the impact of electromagnetic noise and neutron and gamma-ray flashes. Output waveforms were recorded for each laser shot and analyzed offline using a counting method. This approach yielded a spectrum with distinct resonances, which were attributed to 
In and 
Ag, as confirmed through neutron transmission simulation. The spectrum was analyzed using the least-square nuclear-resonance fitting program, REFIT, demonstrating the possibility of using an LDNS for nondestructive areal-density material characterization.
Li-glass detector to gamma rays by a coincidence method伊藤 史哲*; Lee, J.; 弘中 浩太; 高橋 時音; 鈴木 敏*; 持丸 貴則*; 堀 順一*; 寺田 和司*; 小泉 光生
Nuclear Instruments and Methods in Physics Research A, 1064, p.169465_1 - 169465_9, 2024/07
被引用回数：0 パーセンタイル：0.00(Instruments & Instrumentation)The response of a gamma-ray spectrometer is generally determined by analyzing full-energy peaks. However, full-energy peaks cannot be measured easily in the case of scintillation detectors that consist of light elements, such as glass scintillators. Only a strong Compton plateau appears in the spectrum of such detectors. Therefore, Compton edgers were used to evaluate the response of these detectors. The response of a low-resolution Li-glass detector to gamma rays was measured for the first time by a coincidence method with a high-resolution LaBr:Ce detector using cascade gamma rays (2.75 and 1.37 MeV) from a 
Na source. Coincidence gates were applied at the peaks of the spectrum of the LaBr:Ce detector at the 0.51 MeV annihilation peak, and the sum peaks of a gamma ray and a backscattered gamma ray. By analyzing the gated spectra of the Li-glass detector, the energy-dependent detector response (i.e., the output strength and its dispersion) was determined.
Rossi, F.; Lee, J.; 児玉 有; 弘中 浩太; 小泉 光生; 堀 順一*; 寺田 和司*; 佐野 忠史*
Proceedings of 65th Annual Meeting of the Institute of Nuclear Materials Management (Internet), 8 Pages, 2024/07
Various non-destructive assay techniques are being used to verify different nuclear material. However, one of the difficulties of current NDA is the measurement of highly radioactive materials. Since 2015, the JAEA has been working on the development of various active non-destructive assay techniques to address some of the current challenges in nuclear safeguards. Among the various technologies proposed, the Neutron Resonance Analysis system combines signatures from NRTA, NRCA and the newly proposed NRFNA. The combination of those techniques can provide accurate information on the small fissile content in a sample. Neutrons are generated by a pulsed neutron source and slowed down into the moderator. Neutrons are collimated using lead and borated polyethylene to reach the sample, where various neutron-induced reactions occur. n/g PSD plastic scintillators are used to measure the captured gamma rays and fission neutrons at sample location. GS20 is used to collect the transmitted neutrons downstream of the source-sample beamline. A first measurement campaign was performed using natural uranium sample. The possibility of using NRFNA to identify fissile materials within a sample was clearly demonstrated, but the detectors used were not sufficient to achieve a good n/g PSD. New PSD scintillators were introduced. A first measurement campaign was performed in 2023. The acquired data are currently being analyzed, but preliminary results show distinct fission resonance peaks of increasing intensity with varying thicknesses of the same natural uranium samples. Currently, an assembly of multiple scintillators is being investigated to provide a better signal. The new setup will be tested starting in early 2024. In this paper, we will describe in detail the NRA project development and the latest results from experimental campaign. This work is supported by MEXT under the subsidy for the "promotion for strengthening nuclear security and the like"
Lee, J.; 弘中 浩太; 伊藤 史哲*; 小泉 光生; 堀 順一*; 佐野 忠史*
Journal of Nuclear Science and Technology, 61(1), p.23 - 30, 2024/01
被引用回数：6 パーセンタイル：66.64(Nuclear Science & Technology)In the short-distance time-of-flight (TOF) measurements, the background events increase exponentially with decreasing the distance, and the high background increases the uncertainty of the measurement data. The moderated neutron beam includes the time-dependent background originating from the neutron moderator, such as 2.2 MeV gamma rays emitted by 
H(n,) reaction in the moderator. In this paper, to achieve a compact neutron resonance transmission analysis system with high accuracy, we studied the relationship between the moderator and time-dependent background due to gamma rays. Monte Carlo simulations were carried out with the PHITS and the JENDL-4.0 to investigate the time distributions of neutrons and gamma rays emitted from the moderator. Ratios of the gamma-ray intensity to neutron intensity (S/S
ratio) were calculated for various moderators and flight distances. From the obtained results, moderator designs for maintaining low S/S ratio were discussed.
Lee, J.; 児玉 有; Rossi, F.; 弘中 浩太; 小泉 光生; 堀 順一*; 佐野 忠史*
第44回日本核物質管理学会年次大会会議論文集(インターネット), 4 Pages, 2023/11
核不拡散・核セキュリティ総合支援センターでは、試料中に含まれる少量の核分裂性物質を特定し定量する能力を向上させるための技術として、中性子飛行時間法を用いた中性子共鳴核分裂中性子分析(Neutron Resonance Fission Neutron Analysis: NRFNA)の技術開発を進めている。本発表会では、核分裂性物質の非破壊分析のために進めているNRFNA技術の紹介及びその基礎実験の結果について報告する。
Domal, S. J.*; Correa-Alfonso, C. M.*; Paulbeck, C. J.*; Griffin, K. T.*; 佐藤 達彦; 船本 幸代*; Cullings, H. M.*; Egbert, S. D.*; 遠藤 章; Hertel, N. E.*; et al.
Health Physics, 125(4), p.245 - 259, 2023/10
被引用回数：2 パーセンタイル：26.62(Environmental Sciences)原爆被爆者に対する線量評価は、大人・小児・幼児の3体の単純な数学ファントムに基づいて構築されたDS02システムが利用されており、妊婦や胎児に対する詳細な線量評価は行われていかなった。そこで、放射線影響研究所を中心とする日米共同研究チームは、最新の計算科学に基づいて1945年の日本人体型を再現した様々な人体模型(J45シリーズ)を開発し、より精度の高い線量評価を実施してきた。本研究では、様々な週齢の胎児・妊婦人体模型を用いて、その姿勢が被ばく線量に与える影響を検討した。その結果、妊婦の姿勢は、特に胎児の被ばく線量に大きな影響を与えることが分かった。
弘中 浩太; Lee, J.; 小泉 光生; 伊藤 史哲*; 堀 順一*; 寺田 和司*; 佐野 忠史*
Nuclear Instruments and Methods in Physics Research A, 1054, p.168467_1 - 168467_5, 2023/09
被引用回数：5 パーセンタイル：58.89(Instruments & Instrumentation)We propose neutron resonance fission neutron analysis (NRFNA), an active nondestructive assay (NDA) technique, to improve the capability to identify and quantify a small amount of fissile material in a sample. NRFNA uses pulsed neutrons to induce fission reactions in the sample. Fission neutrons are detected by a neutron-gamma pulse shape discrimination (PSD) scintillation detector with time-of-flight (TOF) technique. The obtained nuclide-specific resonance peaks in the neutron energy spectrum provide information to identify and quantify a fissile material in the sample. The possibility of using PSD for NRFNA was confirmed through a test experiment using a natural uranium sample. We successfully observed the resonance peaks from U(n,f) reaction and showed that NRFNA would be useful for measuring a small amount of fissile material in a sample.
Paulbeck, C. J.*; 佐藤 達彦; 船本 幸代*; Lee, C.*; Griffin, K. T.*; Cullings, H. M.*; Egbert, S. D.*; 遠藤 章; Hertel, N. E.*; Bolch, W. E.*
Radiation and Environmental Biophysics, 62(3), p.317 - 329, 2023/08
被引用回数：5 パーセンタイル：40.00(Biology)胎児被ばくした原爆生存者に対する線量評価は、放射線被ばくリスクを評価する上で極めて重要となる。原子力機構、放射線影響研究所、フロリダ大学、米国がんセンターらで構成する研究チームは、これまで、1945年の日本人体型を反映した成人、小児及び胎児を含む妊婦の人体模型を作成し、前方照射や等方照射など理想的な照射条件に対してその被ばく線量を評価してきた。本研究では、原爆線量評価システムDS02に含まれる現実的な照射条件に対して、胎児及び母体の被ばく線量を評価した。その結果、現実的な照射条件においては、胎児の臓器線量は、胎児内での臓器の位置や週齢に大きく依存することが分かった。このような胎児に対する詳細被ばく線量解析結果は、将来の胎児被ばくリスク評価モデルの改訂に役立つと考えられる。
山野 秀将; Chenaud, M.-S.*; Tsige-Tamirat, H.*; Sumner, T.*; Lee, J.*; Liu, S.*; Peregudova, O.*
Proceedings of 30th International Conference on Nuclear Engineering (ICONE30) (Internet), 9 Pages, 2023/05
第4世代炉に関する国際フォーラムは、次世代の原子力エネルギーシステムのための研究開発における国際協力を行うための組織である。第4世代ナトリウム冷却高速炉(SFR)の取り決めの中で、SFRの安全と運転(SO)に関するプロジェクトは、安全技術開発と原子炉運転技術開発の分野を取り扱う。SOプロジェクトの目的には、(1)安全アプローチの構築と具体的な安全設備の性能確認を裏付ける解析及び実験、(2)安全評価と施設の認可に使用される計算ツールの開発と検証及びモデルの妥当性確認、(3)運転中のSFRプラントでの経験と試験から広く得られる原子炉運転技術の取得を含む。SOのテーマに含まれるタスクは、以下の3つのワークパッケージ(WP)、すなわち、WP-SO-1「手法,モデル及びコード」、WP-SO-2「実験計画と運転経験」、及びWP-SO-3「革新的な設計と安全システムの研究」に分類される。本論文では、SOプロジェクトにおける最近の活動を報告する。
