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Abstract

The thermal-hydraulic calculations for the USNRC pressurized thermal shock study, which were performed by the Los Alamos National Laboratory for the Calvert Cliffs nuclear power plant using the TRAC-PF1/MODI code and by the Idaho National Engineering Laboratory for the H.B. Robinson Unit 2 nuclear power plant using the RELAP5/MOD1.6 code, were reviewed at Brookhaven National Laboratory.To quantitatively review these calculations, a simple method based on mass and energy balances was developed at BNL to predict the primary system temperature. In this approach the entire reactor system was lumped into a single volume and the energy balance was applied to that volume. Because significant nonequilibrium effects made it difficult to estimate the pressures, the upper and lower bounds of the pressure were calculated using adiabatic and equilibrium assumptions.In general, the temperatures and pressures of the primary system calculated by both codes were reasonable. The secondary pressures calculated by TRAC indicated it had some difficulty with the condensation model. However, it is not expected that this uncertainty would affect the transient calculations significantly.Review of one typical transient calculation for each plant is discussed in this paper.