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A Condensed Review of the Technology of Post-Accident Heat Removal for the Liquid-Metal Fast Breeder Reactor

M. S. Kazimi, J. C. Chen

Nuclear Technology / Volume 38 / Number 3 / May 1978 / Pages 339-366

Critical Review / dx.doi.org/10.13182/NT78-A32033

The analyses performed to evaluate the capacity to contain the core materials after a hypothetical core meltdown accident are generally grouped under the area of post-accident heat removal (PAHR). Substantial advancement in the state-of-the-art of the PAHR area has occurred within the last few years. The key issues of PAHR, as applied to safety analyses of liquid-metal breeder reactors, are summarized in this Review. The Review includes heat source strength for post-accident conditions, in-vessel core debris retention, ex-vessel core debris retention, and the effects of alternative fuel materials.