Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)
- Volume 7 Issue 4
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- Pages.38-43
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- 2011
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- 1738-8333(pISSN)
DOI QR Code
Development of Green's Functions for Fatigue Damage Evaluation of CANDU Reactor Coolant System Components
CANDU형 원전 주요기기의 피로손상 평가를 위한 그린함수 개발
- Kim, Se Chang ;
- Sung, Hee Dong ;
- Choi, Jae Boong ;
- Kim, Hong Key (KINS) ;
- Song, Myung Ho (KINS) ;
- Nho, Seung Hwan (KINS)
- 김세창 (성균관대학교 기계공학) ;
- 성희동 (성균관대학교 기계공학) ;
- 최재붕 (성균관대학교 기계공학) ;
- 김홍기 (한국원자력안전기술원) ;
- 송명호 (한국원자력안전기술원) ;
- 노승환 (한국원자력안전기술원)
- Received : 2011.11.11
- Accepted : 2011.11.21
- Published : 2011.12.01
Abstract
For the efficient and safe operation of nuclear power plant, evaluating quantitatively aging phenomenon of major components is necessary. Especially, typical aging parameters such as stresses and cumulative usage factors should be determined accurately to manage the lifetime of the plant facility. The 3-D finite element(FE) model is generated to calculate the aging parameters. Mechanical and thermal transfer functions called Green's functions are developed for the FE model with standard step input. The stress results estimated from transfer functions are verified by comparing with 3-D FE analyses results. Lastly, we suggest an effective fatigue evaluation methodology by using the transfer functions. The usefulness of the proposed fatigue evaluation methodology can be maximized by combining it with an on-line monitoring system.
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