Journal of Radiation Industry (방사선산업학회지)

Korean Society of Radiation Industry (한국방사선산업학회)
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Evaluation of Neutron Flux Accounting for Shadowing Effect Among the Dry Storage Casks

경수로 사용후핵연료 건식저장용기 간 중성자 표면선속 간섭률 평가

  • Min Woo Kwak (Department of Nuclear Engineering, Kyung Hee University) ;
  • Shin Dong Lee (Department of Nuclear Engineering, Kyung Hee University) ;
  • Kwang Pyo Kim (Department of Nuclear Engineering, Kyung Hee University)
  • 곽민우 (경희대학교 원자력공학과) ;
  • 이신동 (경희대학교 원자력공학과) ;
  • 김광표 (경희대학교 원자력공학과)
  • Received : 2024.05.29
  • Accepted : 2024.06.17
  • Published : 2024.06.30
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Abstract

The Korean 2nd basic plan for management of high-level radioactive waste presented a plan to manage spent nuclear fuel through dry storage facilities in NPP on-site. For the construction and operation of the facility, it is necessary to develop the monitoring system of the integrity of spent nuclear fuel before operation. NUREG-1536 recommends that the theoretical cask array, typically in the 2×10 array, should account for shadowing effect among the dry storage casks. The objective of this study was to evaluate neutron flux accounting for shadowing effect among dry storage casks. The neutron release rate was evaluated using ORIGEN based on the design basis fuel condition. And the simulation of dry storage casks and evaluation of the shadowing effect were performed using MCNP. Shadowing effect of other dry storage casks was the highest at the center of the dry storage facility of the 2×10 array compared with the outside of the cask. The shadowing effect of neutron flux on the surface among the metal casks was approximately 18% at point 1, 23% at point 2, and 43% at point 3. For the concrete casks, the shadowing effect of neutron flux on the surface was approximately 46% at point 1, 51% at point 2, and 52% at point 3. This means that correction is necessary to monitor the integrity of spent nuclear fuel in each dry storage cask through evaluation of shadowing effect. The results of this study will be used for comparative analysis of neutron measurement data from spent nuclear fuels in dry storage cask. Additionally, the neutron flux evaluation procedure used in this study could be used as the basic data of safety assessment of dry storage cask and development of safety guide.

Keywords

Acknowledgement

본 연구는 한국에너지기술평가원에서 주관하는 에너지 기술개발사업의 일환으로 수행된 연구입니다(No. 2021171020001B).

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