SAC-CFR computer code verification with Experimental Breeder Reactor II loss-of-primary-flow-without-scram tests data

Abstract

A series of tests in the Experimental Breeder Reactor No.2 (EBR-II) have been conducted to investigate the effects of a complete loss of primary flow without scram (LOFWS). In this paper we use a computer code which we have developed, named System Analysis Code for China Fast Reactor (SAC-CFR), which has a three-dimensional hot pool model to analyze the whole-plant transient behavior of the Experimental Breeder Reactor II (EBR-II) under loss of primary flow without scram (LOFWS) tests. The three-dimensional hot pool model code coupled in SAC-CFR was used to analyze flow patterns of the flow filled in Experimental Breeder Reactor II. Among the LOFWS tests, SHRT 45 and SHRT 39 are the most typical accident tests. In this paper, particular emphasis was given to validation of models for predicting SHRT 45 and SHRT 39 tests by SAC-CFR. The predicted results agreed well with measurements which are taken from Experimental Breeder Reactor II loss of primary flow without scram tests data.