Natural Circulation Response of Pressurized Water Reactors
The system responses of pressurized water reactors during the natural circulation mode of decay heat removal are analyzed and evaluated. Selected data from fourteen events at twelve operating plants are presented which compare the thermal-hydraulic responses of Westinghouse, Babcock & Wilcox, and Combustion Engineering designed nuclear steam supply systems to a loss of forced circulation. Most of the events were initiated by a loss of offsite power transient. The first known comparisons of RELAP5 calculations to actual plant data during natural circulation cooling for the various vendor designs are discussed. The results of these comparisons provide criteria that can be used by the operators to confirm that natural circulation has been established and show how operator actions affect natural circulation response.
KeywordsNatural Circulation Pressurize Water Reactor Reactor Coolant Combustion Engineer Safety Injection
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