1990•Transactions of the American Nuclear SocietyRequires access

TRAC loss-of-coolant accident analyses of the Savannah River production reactors

J.F. Lime, F.E. Motley

Abstract

TRAC loss-of-coolant accident (LOCA) analyses were performed as part of the independent safety review of the US Department of Energy's Savannah River (SR) production reactors. The double-ended guillotine break in a coolant loop is a design-basis LOCA for the SR reactors. Three break locations were analyzed to determine the worst break location: (1) at the pump-suction flange; (2) at the pump discharge flange; or (3) at the plenum inlet. The plenum-inlet break was shown to be the most severe in terms of minimum flow delivered to each fuel assembly in the reactor core.

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Key concepts: Plenum space, Nuclear engineering, Coolant, Flange, Environmental science, TRAC, Loss-of-coolant accident, Pressurizer