BWR/4 loss of feedwater transient analysis

This paper presents an analysis of a series of loss of feedwater (LOF) transients for a typical BWR/4 reactor. These calculations were prompted by the events that occurred during the TMI incident and hence include various assumed failures in the safety/relief valve system and the assumed inoperability of various safety systems. This analysis provides transient results necessary to evaluate the potential for core uncovery and excessive average fuel temperatures which can then be used in the evaluation of the adequacy of the engineered safety features and the plant operating procedures. The RELAP5/MOD1 computer code was used for this analysis. The version of the code is designated as Cycle 13 with additional modifications provided by INEL. The modifications affect the jet pump model, interphase drag model and separator model.