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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：1 パーセンタイル：0.00(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：0 パーセンタイル：0.00(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：2 パーセンタイル：64.46(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：4 パーセンタイル：71.02(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。
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：4 パーセンタイル：71.02(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.
余語 覚文*; Lan, Z.*; 有川 安信*; 安部 勇輝*; Mirfayzi, S. R.*; Wei, T.*; 森 隆人*; Golovin, D.*; 早川 岳人*; 岩田 夏弥*; et al.
Physical Review X, 13(1), p.011011_1 - 011011_12, 2023/01
被引用回数：28 パーセンタイル：96.01(Physics, Multidisciplinary)Neutrons are powerful tools for investigating the structure and properties of materials used in science and technology. Recently, laser-driven neutron sources (LDNS) have attracted the attention of different communities, from science to industry, in a variety of applications, including radiography, spectroscopy, security, and medicine. However, the laser-driven ion acceleration mechanism for neutron generation and for establishing the scaling law on the neutron yield is essential to improve the feasibility of LDNS. In this paper, we report the mechanism that accelerates ions with spectra suitable for neutron generation. We show that the neutron yield increases with the fourth power of the laser intensity, resulting in the neutron generation of 
in 
at a maximum, with 
Wcm
, 900 J, 1.5 ps lasers. By installing a "hand-size" moderator, which is specially designed for the LDNS, it is demonstrated that the efficient generation of epithermal (0.1-100 eV) neutrons enables the single-shot analysis of composite materials by neutron resonance transmission analysis (NRTA). We achieve the energy resolution of 2.3% for 5.19-eV neutrons 1.8 m downstream of the LDNS. This leads to the analysis of elements and isotopes within sub-
s times and allows for high-speed nondestructive inspection.
伊藤 史哲*; Lee, J.; 弘中 浩太; 小泉 光生; 余語 覚文*
Proceedings of 19th Annual Meeting of Particle Accelerator Society of Japan (インターネット), p.137 - 140, 2023/01
中性子共鳴透過分析(NRTA)は、パルス中性子を計量したい核物質に照射し、飛行時間(TOF)法を用いて測定核物質を非破壊測定する手法であるが、小型・高精度化には短パルスな小型中性子源が必要となる。近年発展著しいレーザー技術を用いたレー ザー駆動中性子源(LDNS)は、そのような中性子源として将来を期待されている。そこで我々はLDNSを用いたNRTAの技術開発を行い、実証実験を行った。その結果について報告する。
Lee, J.; 伊藤 史哲*; 弘中 浩太; 高橋 時音; 鈴木 敏*; 小泉 光生
Journal of Nuclear Science and Technology, 59(12), p.1546 - 1557, 2022/12
被引用回数：8 パーセンタイル：77.83(Nuclear Science & Technology)Compact time-of-flight (TOF) measurement systems are desirable for easy installation in various facilities. To achieve such compact systems, one of the key considerations is the design of the neutron moderator. However, there are only a few reports on systematic studies on moderators considering both neutron energy resolution as well as a neutron intensity. In this paper, to design an epithermal neutron moderator for short-distance TOF measurements, the neutron intensity and energy resolution of epithermal neutrons have been studied using the Monte Carlo simulation code PHITS with JENDL-4.0 for various types of moderators. The neutronic characteristics of a moderator comprising several components were evaluated. The relationships between the moderator dimensions and both the energy resolution and intensity of the epithermal neutrons were determined. From the obtained results, the appropriate high resolution moderator designs for the short-distance TOF measurements were proposed.
Lee, J.; 伊藤 史哲*; 弘中 浩太; 高橋 時音; 鈴木 敏*; 小泉 光生; 堀 順一*; 寺田 和司*
第43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, 2022/11
中性子検出に広く使われているGS20リチウムガラスシンチレータは、応答は速いがn/g弁別能に乏しい。ガンマ線背景事象を適切に評価するためには、ガンマ線に対する応答特性を知る必要がある。特に中性子測定時は減速材中の水素原子核から発生する2.2MeVのガンマ線が主な背景事象となるが、このような高エネルギーガンマ線への応答特性の報告はほとんどない。このため、本研究では、GS20の応答特性についてNa-24ガンマ線源を用いて調べた。
Lee, J.; 弘中 浩太; 伊藤 史哲*; 高橋 時音; 小泉 光生; 堀 順一*; 寺田 和司*
KURNS Progress Report 2021, P. 97, 2022/07
文部科学省補助金事業「核セキュリティ強化等推進事業費補助金」の下、核不拡散技術開発の一環として、レーザー駆動中性子源(LDNS)を用いたコンパクトな核共鳴透過分析(NRTA)システムの技術開発を行っている。コンパクトなNRTAシステムを構築するためには、中性子の飛行距離を短くすることが重要な要素である。しかし、短距離のTOF測定では、減速材中の水素への中性子捕獲による2.2MeVガンマ線の影響が短距離に比例して指数的に大きくなってしまう。また、LDNSは発展途上であるため、中性子フラックスが十分ではなく、検出効率の高い検出器を用いることが望ましい。このため、我々は、高エネルギーガンマ線に対する検出効率が低く、かつ高い中性子感度を持つ検出器(積層型中性子検出器)を開発してきた。令和3年度の京都大学LINAC実験では、中性子に対する検出効率を上げ、両側にPMTを取り付け、コインシデンス測定によりノイズを除去できるようになった改良型の積層型中性子検出器の性能評価を行い、共鳴TOF測定による良いパフォーマンスを確かめられた。
弘中 浩太; 伊藤 史哲*; Lee, J.; 小泉 光生; 高橋 時音; 鈴木 敏*; 余語 覚文*; 有川 安信*; 安部 勇輝*
第42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, 2021/11
中性子共鳴透過分析(NRTA)はパルス中性子源を用いてTOF測定を行うことで核物質を非破壊測定する手法であるが、小型・高精度化には短パルスな小型中性子源が必要となる。近年発展著しいレーザー技術を用いたレーザー駆動中性子源(LDNS)は、そのような中性子源として将来を期待されている。我々はLDNSを用いたNRTAの実現可能性を調べるため、大阪大学LFEXレーザーを用いて中性子TOF測定実験を行った。
伊藤 史哲*; Lee, J.; 弘中 浩太; 高橋 時音; 鈴木 敏*; 堀 順一*; 寺田 和司*; 小泉 光生
KURNS Progress Report 2020, P. 98, 2021/08
文部科学省補助金事業「核セキュリティ強化等推進事業費補助金」の下、核不拡散技術開発の一環として、レーザー駆動中性子源(LDNS)を用いたコンパクトな核共鳴透過分析(NRTA)システムの技術開発を行っている。NRTAにおいては、パルス中性子源から放出される中性子エネルギーが、飛行時間(TOF)法を用いて測定される。LDNSは、短い飛行距離でも高精度なTOF測定を行うために必要となる、短いパルス幅を持つという特性等から注目されている。短距離TOF測定では、減速材中の水素への中性子捕獲による2.2MeVガンマ線の飛来タイミングと、共鳴エネルギー付近の中性子の飛来タイミングが重なり、大きなガンマ線背景事象が存在することとなる。また、LDNSは発展途上であるため、中性子フラックスが十分ではなく、検出効率の高い検出器を用いることが望ましい。このため、我々は、高エネルギーガンマ線に対する検出効率が低く、かつ高い中性子感度を持つ検出器(多層型中性子検出器)を開発してきた。令和3年度の実験結果の一つとして、多層型中性子検出器が、高エネルギーガンマ線に対して低感度であることが確かめられた。
, 
, 
, and 
Lee, J. Y.*; 谷田 聖; Belle Collaboration*; 他201名*
Physical Review D, 103(5), p.052005_1 - 052005_12, 2021/03
被引用回数：12 パーセンタイル：60.53(Astronomy & Astrophysics)We report branching fraction measurements of four decay modes of the 
baryon, each of which includes an 
meson and a 
baryon in the final state, and all of which are measured relative to the 
decay mode. The results are based on a 
data sample collected by the Belle detector at the KEKB asymmetric-energy 
collider. Two decays, and , are observed for the first time, while the measurements of the other decay modes, and 
, are more precise than those made previously. We obtain 
/
= 
, 
/ = 
, 
/ = 
, and 
/
= 
. The mass and width of the 
are also precisely determined to be 
and 
, respectively, where the uncertainties are statistical and systematic, respectively.
Nguyen, T.-L.*; Lee, M.-W.*; 長谷川 邦夫; Kim, Y.-J.*
Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 7 Pages, 2018/07
軸方向に離れた位置に存在する異なる断面の2個の寸法が同じである周方向亀裂を有する配管の曲げ破壊応力について、亀裂間の軸方向距離Hをパラメータとして、数値解析を行った。その結果、深くて短い亀裂はHが増加すると破壊曲げ応力が増加するが、浅くて長い亀裂はHに依存しないことが分かった。
佐野 忠史*; 堀 順一*; 高橋 佳之*; 八島 浩*; Lee, J.*; 原田 秀郎
EPJ Web of Conferences, 146, p.03031_1 - 03031_3, 2017/09
被引用回数：8 パーセンタイル：96.32(Nuclear Science & Technology)We carried out Monte Carlo calculation to provide energy resolution of pulsed neutron beam for TOF measurements in the KURRI-LINAC pulsed neutron facility. The calculations were performed for moderated neutron flux at the energy range from 0.01 eV to 20 MeV. As the result, we obtained the energy resolutions (
E/E) in the epi-thermal region. For example, the energy resolutions were 1.0% in the neutron energy of 1.0 eV, 1.1% in 100.0 eV and 1.7% in 1.0 keV.
Lee, J. Y.*; 江川 弘行; 長谷川 勝一; 早川 修平; 細見 健二; 今井 憲一; 佐甲 博之; 佐藤 進; 杉村 仁志; 谷田 聖; et al.
JPS Conference Proceedings (Internet), 8, p.021008_1 - 021008_6, 2015/09
A new single-sided silicon micro-strip detector (SSD) is being developed at the J-PARC K1.8 beam line for an emulsion-counter hybrid experiment (J-PARC E07). The SSD will be mainly used for vertex measurements in emulsion plates. Two prototypes of SSD have been fabricated to check the performance of the circuit board and silicon sensors. The first prototype consists of only one layer of a silicon sensor whereas the second prototype consists of two layers of silicon sensors. The final product will be a stack of 4 layers of silicon sensors in the order of 
-
--. The first and second prototypes of SSD have been tested and the final product will be fabricated based on the test result.
