자유낙하충격조건에 있는 사용후핵연료 운반용기의 충격해석방법 연구

Analysis Method on the Free Drop Impact Condition of Spent Nuclear Fuel Shipping Casks

  • 이재형 (충남대학교 기계설계공학과 대학원) ;
  • 이영신 (충남대학교 기계설계공학과 대학) ;
  • 류충현 (충남대학교 기계설계공학과 대학) ;
  • 나재연 (충남대학교 기계설계공학과 대학원)
  • 발행 : 2001.11.01

초록

The package used to transport radioactive materials, which is called by cask, must be safe under normal and hypothetical accident conditions. These requirements for the cask design must be verified through test or finite element analysis. Since the cost for FE analysis is less than one for test. the verification by FE analysis is mainly used. But due to the complexity of mechanical behaviors. the results depends on how users apply the codes and it can cause severe errors during analysis. In this paper, finite element analysis is carried out for the 9 meters free drop and the puncture condition of the hypothetical accident conditions using LS-DYNA3D and ABAQUS/Explicit. We have investigated the analyzing technique for the free drop impact test of the cask and found several vulnerable cases to errors. The analyzed results were compared with each other. We have suggested a reliable and relatively simple analysis technique for the drop test of spent nuclear fuel casks.

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