![]() ![]() A statistical analysis of the dispersion of results is performed afterwards. Results showing the thermal hydraulic behaviour of the primary system and the propagation of core degradation are presented for 124 successful calculations, which is the minimum number of required calculations to estimate a 95/95 tolerance limit at the 3rd order of the Wilks formula application. The number of required calculations is determined by the Wilks formula from the desired percentile and confidence level, and the values of the uncertain parameters are randomly sampled according to appropriate distribution functions. The uncertain parameters are selected based on their impact on the safety criteria, the operation of the NPP safety systems and to de-scribe uncertainties in the initial and boundary conditions. A best estimate plus uncertainty (BEPU) methodology with probabilistic propagation of input uncertainty is used. The station blackout scenario with a small break loss of coolant accident is analyzed, and all processes of the in-vessel phase are covered. The plant model is based on the nuclear power plant (NPP) Krško, a Westinghouse-type power plant. A comprehensive uncertainty analysis in the event of a severe accident in a two-loop pressurized water reactor is conducted using an uncertainty package integrated in the ASYST code.
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