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Suzuki, Mitsuhiro; Anoda, Yoshinari
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
Japan Atomic Energy Research Inst., Tokyo (Japan)2000
AbstractAbstract
[en] A small break loss-of-coolant accident (SBLOCA) in a Westinghouse-type four-loop PWR was simulated in an experiment (SB-CL-24) conducted at the Large-Scale Test Facility (LSTF) with an intention to study repeated core heatup during a long-term cooldown process. The experiment was conducted on February 28, 1990 with specified test conditions including failure assumptions both on the high pressure injection (HPI) and the auxiliary feedwater systems, and the intentional secondary system depressurization as an operator action. The secondary depressurization contributed to promote the primary depressurization and the actuation of accumulator injection system (AIS). A temporary core heatup was observed in each of three loopseal clearing (LSC) processes. A significant core heatup occurred in the following boil-off process after loss of the secondary coolant mass and the AIS termination due to increase of the primary pressure. By additional opening of the pressurizer relief valves and safety valves, the primary pressure rapidly decreased to result in the low pressure injection (LPI) which cooled the heated core. This report summarizes results of the experiment (SB-CL-24) in addition to typical responses of some accident indication systems including the core exit thermocouples (CETs) and the water level meters in the primary system. (author)
Primary Subject
Source
Mar 2000; 188 p; 14 refs., 109 figs., 15 tabs.
Record Type
Report
Report Number
Country of publication
ACCIDENTS, CONTROL EQUIPMENT, COOLING SYSTEMS, ECCS, ENERGY SYSTEMS, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, EQUIPMENT, FLOW REGULATORS, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTOR PROTECTION SYSTEMS, REACTORS, THERMAL REACTORS, VALVES, WATER COOLED REACTORS, WATER MODERATED REACTORS
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