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論文

Utilizing PUNITA experiments to evaluate fundamental delayed gamma-ray spectroscopy interrogation requirements for nuclear safeguards

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:36.29(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.

口頭

Developing delayed gamma-ray spectroscopy for reprocessing plant nuclear safeguards; Neutron detection system development

Lee, H.-J.; Rodriguez, D.; Rossi, F.; 小泉 光生; 高橋 時音

no journal, , 

Under the MEXT research program, The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security of the Japan Atomic Energy Agency is developing Delayed Gamma-ray Spectroscopy (DGS). The DGS instrument irradiates a sample with neutrons to induce fission and then observes gamma rays emitted during the radioactive decay of the fission products. Since DGS uses neutron sources, it is important to monitor these to both confirm the source consistency and normalize delayed gamma-ray spectra. In addition, prompt-fission and delayed neutron signatures can be used to verify the DGS analysis. To do this, $$^{3}$$He and $$^{4}$$He neutron detectors have been investigated. Since the DGS instrument must be compact, the neutron detectors will be close to the neutron sources and fissionable samples within the instrument. Consequently, several characterization studies were performed for short source-detector distances. This paper will describe experimental results with associated simulations, in light of how the neutron detection systems will be integrated into the DGS instrument.

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