TECHNICAL. DESCRIPTION BOILING WATER REACTOR- FULL LENGTH EMERGENCY COOLING HEAT TRANSFER (BWR-FLECHT) TESTS PROJECT

摘要

The Boiling Water Reactor - Full Length Emergency Cooling Heat Transfer (BWR-FLECHT) Tests Project is directed toward experimental investigation of the thermal and hydraulic aspects of terminating the core thermal transient following a loss-of-coolant accident by means of emergency core coolant injection.nThis report provides a technical description of the BWR-FLECHT project. Included in the report are the technical basis for the project, the accomplish¬ments achieved thus far, a detailed test plan, and a description of the facilities.nBWR-FLECHT tests are conducted using full-length 49-rod, electrically heated bundles to simulate nuclear fuel pins. Both stainless steel- and Zircaloy-clad bundles are used, and both core spray and core flooding techniques of emergency core coolant injection are employed. Tests are performed with either steady state or transient power input to the rods. The stainless steel-clad bundles are tested in sequences to obtain parametric heat transfer infor¬mation;whereas, the Zircaloy-clad bundles are tested to determine the behavior of Zircaloy during the ECC phase of a loss-of-coolant accident and to provide demonstrations of ECC system effectiveness.