EFFECT OF BREAK SIZE ON SEVERE CORE DAMAGE BEHAVIOUR FOR VVER 1000 REACTOR WITH THE ASTEC V1 CODE

摘要

Severe accident analysis of a reactor is an important aspect in evaluation of source term. This in turn helps in emergency planning. Analyses have been carried out for WER-1000 (V320) reactor following LOCA along with Station Blackout (SBO). Computer code ASTEC, (jointly developed by IRSN, France, and GRS, Germany) is used for analyzing the transient. This integral code has been designed to be used as reference code for PSA2 studies. LOCA for different break sizes have been analysed. In this paper, ASTEC predictions have been studied for the in-vessel phase of the accident. The predictions of different severe accident parameters like vessel rupture time, hydrogen and corium production etc. for scenarios without hydro-accumulators have been compared.