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자료유형
학술저널
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한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제5호
발행연도
2020.1
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1,022 - 1,028 (7page)

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One of the possible options for spent-fuel management in Korea is pyroprocessing, which is a process forelectrochemical recycling of spent nuclear fuel. Nuclear material accountancy is considered to be asafeguards measure of fundamental importance, for the purposes of which, the amount of nuclearmaterial in the input and output materials should be measured as accurately as possible by means ofchemical analysis and/or non-destructive assay. In the present study, a neutron measurement systembased on the fast-neutron energy multiplication (FNEM) and passive neutron albedo reactivity (PNAR)techniques was designed for nuclear material accountancy of a spent-fuel assembly (i.e., the inputaccountancy of a pyroprocessing facility). Various parameters including inter-detector distance, sourceto-detector distance, neutron-reflector material, the structure of a cadmium sleeve around the closedetectors, and an air cavity in the moderator were investigated by MCNP6 Monte Carlo simulations inorder to maximize its performance. Then, the detector responses with the optimized geometry wereestimated for the fresh-fuel assemblies with different 235U enrichments and a spent-fuel assembly. It wasfound that the measurement technique investigated here has the potential to measure changes inneutron multiplication and, in turn, amount of fissile material

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