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Abnormal Operation Analysis of the Wolsong 2,3,4 Heat Transport System

월성 2,3,4호기 열수송계통의 비정상 운전 해석

Shin, J.C.
신정철

  • Received : 2016.01.07
  • Accepted : 2016.02.29
  • Published : 2016.03.31

Abstract

The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.

Keywords

Liquid Relief Valves;Reactor Operating Condition;ASME Code;CANDU Reactor;Heat Transport System

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