Korean Journal of Metals and Materials (대한금속재료학회지)

The Korean Institute of Metals and Materials (대한금속재료학회)
권호 표지

Statistical Evaluation of Factors Affecting IASCC of Austenitic Stainless Steels for PWR Core Internals

오스테나이트계 스테인리스강 노내 구조물의 조사유기응력부식균열 영향 인자에 대한 통계적 분석

  • Kim, Sung-Woo (Nuclear Materials Research Division, Korea Atomic Energy Research Institute (KAERI)) ;
  • Hwang, Seong-Sik (Nuclear Materials Research Division, Korea Atomic Energy Research Institute (KAERI)) ;
  • Kim, Hong-Pyo (Nuclear Materials Research Division, Korea Atomic Energy Research Institute (KAERI))
  • 김성우 (한국원자력연구원 원자력재료연구부) ;
  • 황성식 (한국원자력연구원 원자력재료연구부) ;
  • 김홍표 (한국원자력연구원 원자력재료연구부)
  • Received : 2009.06.22
  • Published : 2009.12.20
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Abstract

This work is concerned with a statistical analysis of factors affecting the irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels for core internals of pressurized water reactors (PWR). The microstructural and environmental factors were reviewed and critically evaluated by the statistical analysis. The Cr depletion at grain boundary was determined to have no significant correlation with the IASCC susceptibility. The threshold irradiation fluence of IASCC in a PWR was statistically calculated to decrease from 5.799 to 1.914 DPA with increase of temperature from 320 to $340^{\circ}C$. From the analysis of the relationship between applied stress and time-to-failure of stainless steel components based on an accelerated life testing model, it was found that B2 life of a baffle former bolt exposed to neutron fluence of 20 and 75 DPA was at least 2.5 and 0.4 year, respectively, within 95% confidence interval.

Keywords

Acknowledgement

Grant : 노내 구조물 조사유기응력부식균열 관리기술개발

Supported by : 지식경제부

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