Proceedings of the KSME Conference (대한기계학회:학술대회논문집)

The Korean Society of Mechanical Engineers (대한기계학회)
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Pressurized Thermal Shock Re-Evaluation Studies for Korean PWR Plant

국내 가압경수형 원전에 대한 가압열충격 재평가 연구

  • 장성규 (한국전력기술(주) 전력기술개발연구소) ;
  • 김현수 (한국전력기술(주) 전력기술개발연구소) ;
  • 진태은 (한국전력기술(주) 전력기술개발연구소) ;
  • 장창희 (전력연구원 원자력연구실 PSR 그룹)
  • Published : 2001.11.01
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Abstract

The PTS reference temperature of reactor pressure vessel for one of the Korean NPPs has been predicted to exceed the screening criteria before it reaches it's design life. To cope with this issue, a plant-specific PTS analysis had been performed in accordance with the Regulatory Guide 1.154 in 1999. As a result of that analysis, it was found that current methodology of RG. 1.154 was very conservative. The objective of this study is to examine the effects of changing various input parameters and to determine the amount of conservatism of the current PTS analysis method. To do this, based on the past PTS analysis experience, parametric study were performed for various models using modified VISA-II code. This paper discusses the analysis results and recommendations to reduce the conservatism of current analysis method.

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