Korean Journal of Metals and Materials (대한금속재료학회지)

The Korean Institute of Metals and Materials (대한금속재료학회)
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Reliability Prediction of Long-term Creep Strength of Gr. 91 Steel for Next Generation Reactor Structure Materials

미래형 원자로 구조 재료용 Gr. 91 강의 장시간 크리프 강도의 신뢰성 예측

  • Kim, Woo-Gon (Nuclear Materials Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Jae-Young (Mechanical & Automotive Engineering Department, Pukyong National University) ;
  • Yin, Song-Nan (Nuclear Materials Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Dae-Whan (Nuclear Materials Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Ji-Yeon (Nuclear Materials Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Seon-Jin (Mechanical & Automotive Engineering Department, Pukyong National University)
  • 김우곤 (한국원자력연구원 원자력재료개발부) ;
  • 박재영 (부경대학교 기계 자동차 공학과) ;
  • 윤송남 (한국원자력연구원 원자력재료개발부) ;
  • 김대환 (한국원자력연구원 원자력재료개발부) ;
  • 박지연 (한국원자력연구원 원자력재료개발부) ;
  • 김선진 (부경대학교 기계 자동차 공학과)
  • Received : 2011.01.24
  • Published : 2011.04.25
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Abstract

This paper focuses on reliability prediction of long-term creep strength for Modified 9Cr-1Mo steel (Gr. 91) which is considered as one of the structural materials of next generation reactor systems. A "Z-parameter" method was introduced to describe the magnitude of standard deviation of creep rupture data to the master curve which can be plotted by log stress vs. The larson-Miller parameter (LMP). Statistical analysis showed that the scattering of the Z-parameter for the Gr. 91 steel well followed normal distribution. Using this normal distribution of the Z-parameter, the various reliability curves for creep strength design, such as stress-time temperature parameter reliability curves (${\sigma}$-TTP-R curves), stress-rupture time-reliability curves (${\sigma}-t_{r}-R$ curves), and allowable stress-temperature- reliability curves ([${\sigma}$]-T-R curves) were reasonably drawn, and their results are discussed.

Keywords

Acknowledgement

Grant : 미래형원자로시스템

Supported by : 한국연구재단

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