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Abnormal Operation Analysis of the Wolsong 2,3,4 Heat Transport System
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  • Journal title : Journal of Energy Engineering
  • Volume 25, Issue 1,  2016, pp.15-22
  • Publisher : The Korea Society for Energy Engineering
  • DOI : 10.5855/ENERGY.2015.25.1.015
 Title & Authors
Abnormal Operation Analysis of the Wolsong 2,3,4 Heat Transport System
Shin, J.C.;
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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.
Liquid Relief Valves;Reactor Operating Condition;ASME Code;CANDU Reactor;Heat Transport System;
 Cited by
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