The accident scenarios that need to be analyzed within Chapter 15 of a safety analysis report may vary significantly between advanced reactors and the light water reactors that compose the current commercial fleet. In anticipation of identifying scenarios of concern and developing methods for their analysis, correlations may be made to calculations and tests performed in support of the liquid metal and molten salt reactors that have been operated previously within the US. In this paper, we discuss efforts made to compare Chapter 15 considerations for a proposed lead-bismuth cooled reactor to those developed previously for the Fast Flux Test Facility (FFTF) and the GE-Hitachi PRISM reactor. Comparisons were also made with Beyond Design Basis Accidents for FFTF.
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