Abstract
Predictions of coolable geometry adequacy of the Light Water Breeder Reactor (LWBR) core during a hypothetical loss of coolant accident (LOCA) required development of appropriate analysis methods because of the differences between LWBR and current commercial power reactor designs. These differences include thoria-based fuel, thin-walled cladding, and close rod-rod spacing. The analysis methods and their application to LWBR are described for a postulated worst-case combined LOCA-seismic event. Fuel rod behavior is evaluated with respect to maintenance of coolable geometry, which is one of the acceptance criteria specified by the Nuclear Regulatory Commission.
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