Verification of the Radiation Shielding Analysis of Shipping Cask Using Deterministic and Probabilistic Methods

결정론적인 방법과 확률론적인 방법을 이용한 수송용기 방사선차폐해석의 비교 및 검증

  • Yoon, Jeong-Hyoung (Korea Atomic Energy Research Institute Nuclear Environment Management Center) ;
  • Lee, In-Koo (Korea Atomic Energy Research Institute Nuclear Environment Management Center) ;
  • Bang, Kyoung-Sik (Korea Atomic Energy Research Institute Nuclear Environment Management Center) ;
  • Choi, Byoung-Il (Korea Atomic Energy Research Institute Nuclear Environment Management Center) ;
  • Kim, Chong-Kyoung (Department of Nuclear Engineering, Hanyang University)
  • 윤정현 (한국원자력연구소부설 원자력환경관리센터) ;
  • 이인구 (한국원자력연구소부설 원자력환경관리센터) ;
  • 방경식 (한국원자력연구소부설 원자력환경관리센터) ;
  • 최병일 (한국원자력연구소부설 원자력환경관리센터) ;
  • 김종경 (한양대학교 원자력공학과)
  • Published : 1996.03.30

Abstract

In this study, to set-up the calculation method of radiation shielding of the KSC-4 shipping cask which is being used for spent fuel transportation, the pre-existing two calculation methods, deterministic and probabilistic methods were tested. For the first, the DOT4.2 computer code adopting the deterministic theory was applied for the calculation of effective neutron shielding under assumption of continuous wall thickness of the cask. To verify the first results, the probabilistic theory was used as an alternate calculation. In this case MCNP4A computer code adopting the probabilitic theory was used. And same approximation was obtained from the two different shielding calculations. From the results, it could be confirmed that the design and calculation method used for the radiation shielding of the KSC-4 was adequate and sufficiently safe to meet the design and QA requirements of 10CFR71 Appendix H.