한국압력기기공학회 논문집 (Transactions of the Korean Society of Pressure Vessels and Piping)

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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극한 충격하중이 작용하는 사용후핵연료 운반용기의 구조 건전성을 평가하는 유한요소해석 프로그램에 대한 민감도 분석

Sensitivity Analysis to Finite Element Analysis Program to Evaluate Structural Integrity of a Spent Nuclear Fuel Transport Cask Subjected to Extreme Impact Loads

  • 투고 : 2022.11.17
  • 심사 : 2022.12.21
  • 발행 : 2022.12.30
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초록

To investigate the validity of the finite element analysis program to assess structural integrity of a spent nuclear fuel transport cask subjected to extreme impact loads, structural integrity of the cask for the case of an aircraft engine collision is evaluated using three FE analysis programs: Autodyn, Speed and ABAQUS explicit version. As a result of all analyses, it is confirmed that no penetration occurred in the cask wall. Even though the different programs are used, it is identified that there are insignificant differences in the FE analysis variables such as von Mises effective stress and equivalent plastic strain among the programs.

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과제정보

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구사업의 연구결과입니다(No. 2106064).

참고문헌

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