한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)

한국원자력학회 (Korean Nuclear Society)
권호 표지

Procedure of Pressure/Temperature Curves Generation for Brittle Fracture Prevention of Reactor Vessel

  • Park, M. K. (Korea Atomic Energy Research Institute) ;
  • Kim, Y. J. (Korea Atomic Energy Research Institute) ;
  • Kim, J. M. (Korea Atomic Energy Research Institute) ;
  • Jheon, J. H. (Korea Atomic Energy Research Institute) ;
  • Kim, I. K. (Korea Atomic Energy Research Institute)
  • 발행 : 1996.05.01
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초록

The purpose of this study is to establish the pressure/temperature curves of Reactor Coolant System for brittle fracture prevention. The pressure/temperature curve is the basis to select RC Pump and limits to operate the plant. Based on the plant operation experience, this curve should be re-generated periodically in order to ensure the structural integrity using data from the test of reactor vessel surveilance materials to compensate for the irradiation effects. This study provides the procedure of pressure/temperature curve generation in term of brittle fracture prevention of reactor vessel. Using the UCN 3&4 data, the sample pressure/temperature curve was generated, and it was compared with those of YGN 3&4 based on the stress and $RT_{NDT}$value.

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