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Statistical Life Prediction on IASCC of Stainless Steel for PWR Core Internals

가압형 경수로 스테인리스강 내부 구조물의 조사유기 응력부식균열에 대한 통계적 수명 예측

  • Kim, Sung-Woo (Nuclear Materials Division, Korea Atomic Energy Research Institute) ;
  • Hwang, Seong-Sik (Nuclear Materials Division, Korea Atomic Energy Research Institute) ;
  • Lee, Yeon-Ju (Nuclear Materials Division, Korea Atomic Energy Research Institute)
  • 김성우 (한국원자력연구원 원자력재료개발부) ;
  • 황성식 (한국원자력연구원 원자력재료개발부) ;
  • 이연주 (한국원자력연구원 원자력재료개발부)
  • Received : 2012.02.15
  • Published : 2012.08.25

Abstract

This work is concerned with a statistical approach to the life prediction on irradiation-assisted stress corrosion cracking (IASCC) of stainless steel (SS) for core internals of a pressurized water reactor (PWR). The previous results of the time-to-failure of IASCC measured on neutron-irradiated stainless steel components were statistically analyzed in terms of stress and irradiation. The accelerating life testing model of IASCC of cold worked Type 316 SS was established based on an inverse power model with two stress-variables, the applied stress and irradiation dose. Considering the variation of the yield strength and applied stress with the irradiation dose in the model, the remaining life of the baffle former bolt was statistically predicted during operation under complex environments of stress and irradiation.

Keywords

Acknowledgement

Grant : 장수명 안전성 확보를 위한 원자로 내부구조물 열화 평가기술 개발

Supported by : 지식경제부

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