METAL-WATER REACTIONS: VIII. PRELIMINARY CONS I DERATION OF THE EFFECTS OFAZIRCALOY-WATER REACTION DURING A LOSS OF COOLANT ACCIDENT IN A NUCLEAR REACTOR

摘要

Two preliminary analyses have been made to determine the effect of a chemical reaction between steam and the fuel cladding in a nuclear reactor during a severe loss of coolant accident and prior to melting of the cladding. Pressurized water reactor configuration with rod type, Zircaloy clad, low enriched UO2 fuel elements was used to obtain core parameters for the evaluations. The results of the first analysis indicated core conditions such that the addition of chemical reaction heat would aggravate damage to the reactor, and provided a guide for evaluating various relationships and input data to develop an improved method of analysis.