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Rodriguez, D.; 小泉 光生; Rossi, F.; 瀬谷 道夫; 高橋 時音; Bogucarska, T.*; Crochemore, J.-M.*; Pedersen, B.*; 高峰 潤
Journal of Nuclear Science and Technology, 57(8), p.975 - 988, 2020/08
被引用回数：3 パーセンタイル：47.69(Nuclear Science & Technology)Present safeguards verification methods of high-radioactivity nuclear material use destructive analysis techniques since passive nondestructive techniques are incapable of determining the nuclear material content. To improve this verification process, the JAEA and EC-JRC Ispra, Italy have been collaborating to develop delayed gamma-ray spectroscopy for composition analysis of the fissile nuclides as an aspect of the MEXT subsidy for improving nuclear security and the like. Multiple experiments were performed over three years using PUNITA to interrogate U and Pu samples to determine the signature from the short-lived fission products. We observed many gamma rays useful to determine the composition of a mixed nuclear material sample. Presented here are the results of these measurements with correlations to the interrogation, mass, volume, and sample homogeneity.
小泉 光生; Rossi, F.; Rodriguez, D.; 高峰 潤; 瀬谷 道夫; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.
EUR-28795-EN (Internet), p.868 - 872, 2017/00
Under the collaboration between the Japan Atomic Energy Agency (JAEA) and European Commissions' Joint Research Center (EC-JRC), development of four active neutron-interrogation non-destructive assay methods for nuclear non-proliferation and safeguards are in progress. The techniques are differential die-away analysis, delayed gamma-ray analysis (DGA), neutron resonance transmission analysis, and prompt gamma-ray analysis. Information obtained by each method is used complementarily to characterize a sample. DGA utilizes moderated pulsed neutrons from a D-T neutron generator to induce fission reaction of nuclear materials. Delayed gamma rays from the fission products (FP) are measured to determine the ratios of fissile nuclides (e.g. 
U, and 
Pu) in the sample. Experimental studies of the DGA method are in progress with the Pulsed Neutron Interrogation Test Assembly (PUNITA) in EC-JRC Ispra. Here we present an overview of the study plan of these DGA experiments along with the latest results. This research was implemented under the subsidiary for nuclear security promotion of MEXT.
古川 和男; 塚田 甲子男*
JAERI-M 83-050, 43 Pages, 1983/03
溶融塩ターゲットとブランケツトを加速器増殖炉に利用することが検討された。この塩の中にはThF
,UFが高い濃度で含まれる。この方式の利点は、ターゲットの製作、設計、照射損傷、熱除去、安全性、経済性に関連する。LiF-BeF
-ThF,LiF-NaF-ThF,LiF-BeF-UFなどをターゲット・ブランケット兼用で使うならば、予期以上の中性子発生効率がえられることが、ニュトロニックスから示された。この加速器溶融塩増殖炉(AMSB)の概要、特性、炉化学問題点が紹介された。また、エネルギー戦略上の位置付け、特にトリウムサイクル実現化における貢献などか諭じられた。
