Computational Structural Engineering (전산구조공학)

Computational Structural Engineering Institute of Korea (한국전산구조공학회)
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Maximum Allowable $RT_{NDT}$ of Nuclear Reactor Vessel for Pressurized Thermal Shock Accident

가압열충격 사고에 대한 원자로 용기의 최대 허용 기준무연성천이온도

  • 정명조 (원자력안전기술원 기계설비실) ;
  • 박윤원 (원자력안전기술원 기술개발실) ;
  • 송선호 (원자력안전기술원 기계설비실)
  • Published : 1998.03.01
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Abstract

A small break loss of coolant accident is postulated as a pressurized thermal shock accident in this study. From the temperature and pressure histories of coolant, distributions of the temperature and stress in a vessel wall are analytically calculated. The stress intensity factor and fracture toughness of the vessel wall are determined at the crack tip using the ASME code method and they are compared to check if cracking is expected to occur during the transient postulated. The maximum allowable reference nil-ductility transition temperatures are determined for various crack sizes and the results are discussed.

본 연구에서는 가압열충격 사고로 소형 냉각재 상실사고를 가정하여 냉각재의 온도와 압력의 이력으로 부터 용기 벽의 온도분포를 구하고, 이로 부터 열응력과 압응력을 해석적으로 구하였다. 또 균열 선단에서의 응력강도계수와 파괴인성치를 ASME코드의 방법을 이용하여 구하였고, 이들을 시간에 따라 비교하여 균열의 진전여부를 평가하였다. 원자로 용기 벽에 존재하는 여러 형태의 균열이 견딜 수 있는 최대 기준무연성천이온도를 결정하였으며 평가 결과에 대하여 고찰하였다.

Keywords

References

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