(A) simulation stydy of the emergency core cooling system for the "Ko Ri nuclear power plant

Abstract

The general characteristics of the loss of coolant accident (LOCA) for pressurized water reactor systems(PWR) is reviewed and the emergency core cooling system(ECCS) of the ``$\mbox{\underline{Ko Ri}}$ nuclear power plant unit 1`` and its time response characteristics against LOCA are investigated. For the simulation analysis, a modified version of ``RELAP-4``, a computer program for the transient analysis of PWR following LOCA is run using the parameters of ECCS of the ``$\mbox{\underline{Ko Ri}}$ nuclear power plant unit 1``. In this computation, a cold- leg double-ended severance rupture is postulated. The result of the simulation computation is compared with those of similar studies for other PWR systems.