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Probabilistic Safety Assessment of ESBWR gravity driven cooling system

Kaszko Aleksej, Niewiński Grzegorz, Stępień Michał

Modern Engineering

2020

18--25

According to Polish nuclear law, newly emerging nuclear facilities require probabilistic safety assessment (PSA). This article is intended to present the PSA method and to present the error tree method by which the probability of unavailability of the gravity reactor cooling system (GDCS) of the ESBWR power plant designed by GE Hitachi was determined. This work includes creatiion process of a damage tree and performing a quantitative analysis in SAPHIRE tool and estimating uncertainty using the Monte Carlo method. As a part of the work, it was shown that in the probability of failure of a single GDCS P LINE-A line, the most important element are the basic events related in particular to the operation of service valves.

Risk analysis of external hydrological hazards with flooding potential for a German nuclear reference site

Röwekamp M., Gänssmantel G., Peschke J., Strack C., Utschick M.

Journal of Polish Safety and Reliability Association

2018

Vol. 9, No. 3

65--74

Probabilistic Safety Analyses (PSA) are a supplementary analytical tool used worldwide more and more in order to quantitatively assess the effect of hazards on the overall result regarding the safety of industrial installations, in particular nuclear power plants. In that way PSA provides a reliable basis for decisions on the necessity and the benefits of safety improvements. In the recent past, the existing methods and tools with respect to determining the site-specific risk of nuclear power plants have been comprehensively extended and further enhanced. The focus of extending the existing PSA methods was on external hydrological hazards with flooding potential. For systematically considering hydrological hazards within PSA a systematic approach has been developed. The paper demonstrates the extended approach in the example of a nuclear power plant site with different flooding risks.