An Analysis of Proposed BWR Inlet Flow Blockage Experiments Using Mayu-4b.

摘要

The purpose of this report is to present an analytical study of hypothetical boiling water reactor (BWR) inlet flow blockage accidents. To this end, MAYU-4, a one-dimensional drift-flux digital computer code, was modified to account for nonequilibrium vapor generation, radiation heat transfer, rod bundle countercurrent-flow-limited phenomena, and the exothermic metal-water reaction of the cladding. The revised code, MAYU-4b, was used to investigate postulated BWR inlet flow blockage events and the feasibility of such testing in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory.