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

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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정상운반조건 해석을 위한 사용후핵연료집합체 유한요소모델 최적화

Optimization of Spent Nuclear Fuel Assembly Finite Element Model for Normal Transportation Condition Analysis

  • 김민식 (경희대학교 원자력공학과) ;
  • 박민정 (경희대학교 원자력공학과) ;
  • 장윤석 (경희대학교 원자력공학과)
  • Min Seek Kim ;
  • Min Jeong Park ;
  • Yoon-Suk Chang
  • 투고 : 2023.11.17
  • 심사 : 2023.12.18
  • 발행 : 2023.12.30
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초록

Since spent nuclear fuel assemblies (SFA) are transported to interim storage or final disposal facility after cooling the decay heat, finite element analysis (FEA) with simplification is widely used to show their integrity against cladding failure to cause dispersal of radioactive material. However, there is a lack of research addressing the comprehensive impact of shape and element simplification on analysis results. In this study, for the optimization of a typical pressurized water reactor SFA, different types of finite element models were generated by changing number of fuel rods, fuel rod element type and assembly length. A series of FEA in use of these different models were conducted under a shock load data obtained from surrogate fuel assembly transportation test. Effects of number of fuel rods, element type and length of assembly were also analyzed, which shows that the element type of fuel rod mainly affected on cladding strain. Finally, an optimal finite element model was determined for other practical application in the future.

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참고문헌

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