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Omer, M.; 静間 俊行*; 羽島 良一*; 小泉 光生
Journal of Applied Physics, 135(18), p.184903_1 - 184903_10, 2024/05
被引用回数：0 パーセンタイル：0.00(Physics, Applied)We report on the findings of a quantitative nondestructive analysis of the natural isotopic abundances of hafnium and tungsten elements using nuclear resonance fluorescence. Commercial samples of hafnium and tungsten were irradiated to six quasi-monochromatic 
-ray beams generated by laser Compton scattering in the energy range of 2.4-3.2 MeV. Multiple nuclei were simultaneously excited at each of the six -ray beam energies. A high-purity germanium detector array detected deexcitations of the nuclei. In total, 
transitions were unprecedentedly employed to estimate the isotopic abundances of heavy elements nondestructively. The estimated abundances of three hafnium isotopes and three tungsten isotopes are consistent with standard known natural abundances within the experimental uncertainties. The deviation from the standard values ranges from 0.18% to 1.36%. This work is a contribution of the Japan Atomic Energy Agency (JAEA) to the International Atomic Energy Agency (IAEA) under the agreement of the coordinated research program (CRP), J02015 (Facilitation of Safe and Secure Trade Using Nuclear Detection Technology - Detection of RN and Other Contraband). This work was a part of a study of the nuclear resonance fluorescence aiming at nuclear security and safeguards applications, being supported by the subsidiary for "promotion of strengthening nuclear security or the like" of the Ministry of Education, Culture, Sports, Science, and Technology (MEXT), Japan.
Rodriguez, D.; Rossi, F.; 高橋 時音
IEEE Transactions on Nuclear Science, 71(3), p.255 - 268, 2024/03
被引用回数：0 パーセンタイル：0.00(Engineering, Electrical & Electronic)Under the MEXT subsidy to improve nuclear security related capabilities, we are developing the delayed gamma-ray spectroscopic analysis technique. One goal is to develop an inverse Monte Carlo analysis method using spectra from simulations of the interrogation instrument for comparison to the actual measured spectra. This work presents the validity of the Monte Carlo foundation of the analysis compared to experimental results and other simulation codes.
土屋 晴文; 藤 暢輔; 大図 章; 古高 和禎; 北谷 文人; 前田 亮; 米田 政夫
Journal of Nuclear Science and Technology, 60(11), p.1301 - 1312, 2023/11
被引用回数：2 パーセンタイル：65.72(Nuclear Science & Technology)An integrated active neutron non-destructive analysis (NDA) system, Active-N, was developed to gain knowledge of active neutron NDA techniques that are applicable to measurements of nuclear materials in highly radioactive nuclear fuels. Active-N, equipped with a D-T neutron generator, combines three complementary active neutron NDA techniques: Differential Die-away Analysis (DDA), Prompt Gamma-ray Analysis (PGA), and Neutron Resonance Transmission Analysis (NRTA). In this paper, we provide an overview of Active-N and then demonstrate that the compact NRTA system in Active-N can quantify nuclear materials. Monte Carlo simulations were conducted to determine the design of the compact NRTA system including a moderator, flight tubes, and a detector shield. To investigate how accurately the compact NRTA system determines areal densities in a sample, measurements were performed with a Pu pellet-type sample as well as metallic plate samples of In and Ag. The experimental areal densities of 
Pu, 
In and 
Ag were consistent with those calculated for the individual nuclei. These results show that it is feasible to develop a compact NRTA system capable of determining the contents of nuclear materials in nuclear fuels. This research was implemented under the subsidy for nuclear security promotion of MEXT.
古高 和禎; 大図 章; 藤 暢輔
Nuclear Engineering and Technology, 55(11), p.4002 - 4018, 2023/11
被引用回数：1 パーセンタイル：41.04(Nuclear Science & Technology)An integrated neutron interrogation system has been developed for non-destructive assay of highly radioactive special nuclear materials, to accumulate knowledge of the method through developing and using it. The system combines a differential die-away (DDA) measurement system for the quantification of nuclear materials and a prompt gamma-ray analysis (PGA) system for the detection of neutron poisons which disturb the DDA measurements; a common D-T neutron generator is used. A special care has been taken for the selection of materials to reduce the background gamma rays produced by the interrogation neutrons. A series of measurements were performed to test the basic performance of the system. The results show that the DDA system can quantify plutonium of as small as 20~mg and it is not affected by intense neutron background up to 4.2~TBq and gamma ray of 2.2~TBq. As a result of the designing of the combined system as a whole, the gamma-ray background counting rate at the PGA detector was reduced down to 
s
even with the use of the D-T neutron generator. The test measurements show that the PGA system is capable of detecting less than 1~g of boron compound and about 100~g of gadolinium compound in~30 min. This research was implemented under the subsidy for nuclear security promotion of MEXT.
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：2 パーセンタイル：41.04(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.
Grazzi, F.*; Cialdai, C.*; Manetti, M.*; Massi, M.*; Morigi, M. P.*; Bettuzzi, M.*; Brancaccio, R.*; Albertin, F.*; 篠原 武尚; 甲斐 哲也; et al.
Rendiconti Lincei. Scienze Fisiche e Naturali, 32(3), p.463 - 477, 2021/09
被引用回数：5 パーセンタイル：23.01(Multidisciplinary Sciences)In this paper, we have studied an additively manufactured metallic component, intended for ultra-high vacuum application, the exit-snout of the MACHINA transportable proton accelerator beam-line. Metal additive manufacturing components can exhibit heterogeneous and anisotropic microstructures. Two non-destructive imaging techniques, X-ray computed tomography and Neutron Tomography, were employed to examine its microstructure. They unveiled the presence of porosity and channels, the size and composition of grains and intergranular precipitates, and the general behavior of the spatial distribution of the solidification lines. While X-ray computed tomography evidenced qualitative details about the surface roughness and internal defects, neutron tomography showed excellent ability in imaging the spatial density distribution within the component. The anisotropy of the density was attributed to the material building orientation during the 3D printing process. Density variations suggest the possibility of defect pathways, which could affect high vacuum performances. In addition, these results highlight the importance of considering building orientation in the design for additive manufacturing for UHV applications.
土屋 晴文; 北谷 文人; 藤 暢輔; Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*
Proceedings of INMM 59th Annual Meeting (Internet), 6 Pages, 2018/07
In fields of nuclear safeguards and nuclear security, non-destructive assay (NDA) techniques are needed in order to quantify special nuclear materials (SNMs) in nuclear fuels. Among those techniques, active NDA ones would be preferable to passive ones. One candidate of active NDA techniques is neutron resonance transmission analysis (NRTA). In fact, experiments done at GELINA have shown that NRTA has high potential enough to quantify SNMs in complex materials. Currently, such a NRTA system requires a large electron accelerator facility to generate intense neutron sources. In other words, it is very difficult to perform NRTA at various facilities that need to measure SNMs. Thus, downsizing a NRTA system would be one solution of its difficulty. In order to realize a compact NRTA system, we develop a prototype with a D-T neutron generator that has a pulse width of 10 
s. For this aim, numerical calculations to optimize the compact NRTA system were done. In addition, NRTA measurements with simulated fuel pins were made at neutron time-of-flight facilities such as GELINA. In this presentation, we present results of the numerical calculations and the experimental results. On the basis of those results we discuss a future prospect of a compact NRTA system that would be applicable to SNM quantification. This research was implemented under the subsidiary for nuclear security promotion of MEXT.
薗田 暁; 冨樫 喜博; 宮内 正勝; 岡崎 修二*
JAERI-Tech 99-043, 16 Pages, 1999/05
核物質の計量管理及び保障措置分析における溶液試料に適用可能な高精度の非破壊分析法の確立のため、原研では、米国・DOEとの研究協力協定のもと、ハイブリッドK吸収端/蛍光X線濃度計(HKED)をNUCEFに設置し、溶液試料中のウラン及びプルトニウムの非破壊測定技術の共同開発を進めている。HKEDは査察機器として使用される予定であるため、装置が破壊分析法と同様の測定精度を持ち長期にわたり安定した測定ができなければならない。本報告書は、HKEDの長期安定性及び装置の健全性を示すための標準の長期安定性、さらに試験を通して得られたX線管の出力変動が測定結果に与える影響についてまとめたものである。
中西 友子*; 岡野 健*; 唐鎌 勇*; 石原 猛*; 松林 政仁
Holzforschung, 52(6), p.673 - 676, 1998/00
4種類の杉の胸の高さから1cm厚の小口材を採取し、乾燥過程における水分の像を得るために熱中性子ラジオグラフィ撮影を行った。水分量の変化は撮影後の画像から画像解析により求めた。その結果、初期の水分分布には3種類あり、第一は、心材と辺材の間に位置する白線帯を除き一様に水分が分布しているもの、第二は、白線帯における水分分布は類似しているものの、水分が低下している領域が辺材方向に伸びているものであり、第三は、辺材部と心材部の水分量が各々高低となっているものである。心材部における水分含量が高い場合には、乾燥過程において心材部の水分量が残存する傾向が示された。
安達 武雄; 中原 嘉則; 河野 信昭; 郡司 勝文; 鈴木 敏夫; 園部 保; 大貫 守; 加藤 金治; 立川 圓造; 井上 伸*; et al.
Journal of Nuclear Science and Technology, 31(10), p.1119 - 1129, 1994/10
被引用回数：8 パーセンタイル：59.96(Nuclear Science & Technology)ガドリ入り燃料から切り出された5個のグラム量使用済燃料試片の破壊分析を行い、アクチノイド及びFP核種を定量した。これらの分析値を用いて核設計コード(CASMO)と燃焼計算コード(ORIGEN-2)の両計算値の精度評価を行った。主要核分裂性核種(U,
Pu,
Pu)についてのCASMOの計算値は、約3%以内と実測値に非常に良く一致した。一方OROGEN-2の計算値は、UO
燃料に対して約5%、GdO
-UO燃料に対して約12%といずれも低い値を示した。この12%の過小評価は、ORIGEN-2の計算では、Gdの効果を考慮していないためであると考えられる。その他のマイナーアクチノイドについては、両計算コード間に大差はなく10%前後であったが試験間での変動が大きかった。FPについては、
Eu及び
Sbが非常に大きなくい違いを示した。
竹田 辰興; 永嶺 謙忠*; 山崎 泰規*; 門野 良典*; 石田 勝彦*; 上村 正康*; 山崎 良成*; 水本 元治
日本原子力学会誌, 34(12), p.1098 - 1107, 1992/12
被引用回数：0 パーセンタイル：0.00(Nuclear Science & Technology)ミュオンを用いた種々の科学研究が盛んになってきた。これらは、多くの場合、正負のミュオンが、それぞれ、「軽い陽子」及び「重い電子」として振る舞う、特質を十分に生かしたものである。その対象は、SR法による物性・材料研究、ミュオン触媒核融合研究、ミュオン原子X線による非破壊元素分析、基礎物理学研究等に及ぶ。本解説では、これらについて、最近の興味ある話題について概観し、また、ミュオン科学の進展に大きな寄与が期待される低速ミュオン生成の研究、及び大強度加速器の開発についても触れる。
田村 則
Radiochem.Radioanal.Lett., 18(3), p.135 - 142, 1974/03
非破壊中性子放射化分析により、石炭およびベリリウム中の微量元素を多元素同時定量する方法を確立した。試料と同時に照射した標準コバルトを使って中性子束を決定し、各元素量は核データの文献値を使って放射化計算式から求める。この方法による定量値を他の方法で得られた分析値と比較して、本法による定量の正確さを吟味した。その結果、日常分析として十分満足できる正確さで定量できることがわかった。
Omer, M.; 静間 俊行*; 羽島 良一*; 小泉 光生
no journal, ,
A quantitative isotopic analysis of the natural metallic samples of hafnium (Hf) and tungsten (W) elements is presented. Hf and W targets were exposed to quasi-monochromatic -ray beams generated by laser Compton scattering (LCS) at the high intensity -ray source (HIS) facility of Duke University. The -ray beams, in the 2.4-3.2 MeV energy range, excited multiple nuclides simultaneously via the nuclear resonance fluorescence (NRF). All excited transitions were employed to analyze the isotopic compositions of the targets. Particularly, the content of the even-mass naturally occurring isotopes of Hf and W was detected with high precision. The uncertainty of the measured abundances is 2.7-6.7%, while the deviation from the reference values ranges between 0.18-1.36%. This work is a contribution of the JAEA to the International Atomic Energy Agency (IAEA) under the agreement of the coordinated research program (CRP), J02015 (Facilitation of Safe and Secure Trade Using Nuclear Detection Technology - Detection of RN and Other Contraband). This work was a part of a study of the nuclear resonance fluorescence aiming at nuclear security and safeguards applications, being supported by the subsidiary for "promotion of strengthening nuclear security or the like" of the Ministry of Education, Culture, Sports, Science, and Technology (MEXT), Japan.
Lan, Z.*; Wei, T.*; 早川 岳人*; 加美山 隆*; 佐藤 博隆*; 有川 安信*; Mirfayzi, S. R.*; 小泉 光生; 安部 勇輝*; Morace, A.*; et al.
no journal, ,
A Laser-Driven Neutron Source (LDNS) is a novel neutron that provides neutron beam of ultra-short pulse duration and high flux. This technique would be useful for neutron resonance non-destructive diagnosis application. A demonstration experiment was carried out using an LDNS developed for the LFEX laser of Institute of Laser Engineering, Osaka University. A neutron resonance spectrum was observed with a single laser shot. The technique can be used as a "nuclear thermometer" because the resonance shape is broadened as a function of the sample material temperature.
土屋 晴文; Guembou Shouop C.; 北谷 文人
no journal, ,
Neutron Resonance Transmission Analysis (NRTA) is a promising nondestructive analysis (NDA) method capable of measuring various nuclear materials (NMs) with high accuracy. NRTA thus has been garnering attention as a method to reduce material unaccounted for (MUF) in material accountancy and enhance detection capabilities for concealed NMs at ports and airports. However, the large sizes of existing NRTA systems make them impractical for installation in nuclear facilities with limited spaces. To overcome this situation, we develop a table-top NRTA system using a 
Cf neutron source. In this presentation we will outline our advancements in NRTA development to date and introduce the structure of the table-top NRTA system currently in progress. This research was implemented under the subsidy for nuclear security promotion of MEXT.
