Severe Accident Risks: An Assessment of Five U.S. Nuclear Power
Plant,Individual Plant Examination Report for San Onofre Nuclear Generating Station Units 2 and 3
,In this paper, the reactor core cooling and its melt progression terminating is evaluated, and the initiation criterion for reactor cavity flooding during water injection is determined. The core cooling in pressurized-water reactor of severe accident is simulated with the thermal hydraulic and severe accident code of SCDAP/RELAP5. The results show that the core melt progression is terminated by water injection, before the core debris has formed at bottom of core, and the initiation of reactor cavity flooding is indicated by the core exit temperature.
Severe Accident Risks: An Assessment of Five U.S. Nuclear Power
Plant,Individual Plant Examination Report for San Onofre Nuclear Generating Station Units 2 and 3
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