Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Evaluation of Reference Temperature on Pressurized Thermal Shock for Domestic Pressurized Water Reactors

국내 가압경수형 원자로에 대한 가압열충격 기준온도 평가

  • 최영환 (한국원자력안전기술원 공학연구실) ;
  • 박정순 (한국원자력안전기술원 공학연구실) ;
  • 정명조 (한국원자력안전기술원 공학연구실)
  • Published : 2010.12.01
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Abstract

The evaluation method for the failure frequency of reactor vessel under pressurized thermal shock(PTS) is developed using probabilistic fracture mechanics. The probabilistic reactor integrity evaluation code, named R-PIE code, is developed. The validity and uncertainty of the R-PIE code is investigated. The reactor failure frequencies under PTS for Kori-1 nuclear power plant and other type of domestic nuclear power plants are evaluated. The reference PTS temperature for domestic nuclear power plants is obtained for the rule making against PTS failure.

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