Probabilistic Safety Analysis of NPP with the BREST-OD-300 Reactor

BREST-OD-300, an innovative inherent safety fast reactor, is being developed as a pilot and demonstration prototype for the basic commercial reactor facilities of future nuclear power with a closed nuclear fuel cycle. As part of the PSA level 1 with the BREST-OD-300 reactor the following main tasks have been solved: • selection and grouping of initial events; • identification of success criteria (SC) for the modeled functions; • analysis of emergency sequences; • analysis of systems; • data analysis; • analysis of the PSA results. The obtained CDF value (9.0∙10^-9 1/year) satisfies to the target values in NP-001-15 both for the total probability of severe accidents (10^-5) in an interval of 1 year and the total probability of a major emergency release (10^-7) in an interval of 1 year. (author)