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

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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반복 유한요소 결함 성장 해석을 위한 결함 모델링 및 응력확대계수 계산 절차의 타당성 검증

Validation of Crack-Tip Modeling and Calculation Procedure for Stress Intensity Factor for Iterative Finite Element Crack Growth Analysis

  • Gi-Bum Lee (서울과학기술대학교 기계시스템디자인공학과) ;
  • Youn-Young Jang (서울과학기술대학교 기계시스템디자인공학과) ;
  • Nam-Su Huh (서울과학기술대학교 기계시스템디자인공학과) ;
  • Sunghoon Park ((주)브이이엔지) ;
  • Noh-Hwan Park ((주)브이이엔지) ;
  • Jun Park ((주)브이이엔지)
  • 투고 : 2021.05.30
  • 심사 : 2021.06.18
  • 발행 : 2021.06.30
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초록

As the material aging of nuclear power plants has been progressing in domestic and overseas, crack growth becomes one of the most important issues. In this respect, the crack growth assessment has been considered an essential part of structural integrity. The crack growth assessment for nuclear power plants has been generally performed based on ASME B&PV Code, Sec. XI but the idealization of crack shape and the conservative solutions of stress intensity factor (SIF) are used. Although finite element analysis (FEA) based on iterative crack growth analysis is considered as an alternative method to simulate crack growth, there are yet no guidelines to model the crack-tip spider-web mesh for such analysis. In this study, effects of various meshing factors on FE SIF calculation are systematically examined. Based on FEA results, proper criteria for spider-web mesh in crack-tip are suggested. The validation of SIF calculation method through mapping initial stress field is investigated to consider initial residual stress on crack growth. The iterative crack-tip modeling program to simulate crack growth is developed using the proposed criteria for spider-web mesh design. The SIF results from the developed program are validated by comparing with those from technical reports of other institutes.

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과제정보

본 논문은 한국수력원자력(주)에서 재원을 부담하여 수행한 연구결과 입니다. (NO. 제2019-기술-07호)

참고문헌

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