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Performance of Metal and Oxide Fuel Cores During Accidents in Large Liquid-Metal-Cooled Reactors

Peter H. Royl, James E. Cahalan, Günter Friedel, Günter Kussmaul, Jean Moreau, Maurice Perks, Roald A. Wigeland

Nuclear Technology / Volume 97 / Number 2 / February 1992 / Pages 198-211

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34616

In a cooperative effort among European and U.S. analysts, an assessment of the comparative safety performance of metal and oxide fuels during accidents in a 3500-MW(thermal), pool-type, liquid-metal-cooled reactor (LMR) is performed. The study focuses on three accident initiators with failure to scram: the unprotected loss-of-flow (ULOF), the unprotected transient overpower, and the unprotected loss-of-heat-sink (ULOHS). Core designs with a similar power output that have been previously analyzed in Europe under ULOF accident conditions are also included in this comparison. Emphasis is placed on identification of design features that provide passive, self-limiting responses to postulated accident conditions and quantification of relative safety margins. The analyses show that in ULOF and ULOHS sequences, metal-fueled LMRs with pool-type primary systems provide larger temperature margins to coolant boiling than do oxide-fueled reactors of the same design.