Validation of Coupled Codes for VVER Reactors by Analysis of Plant Transients

Three-dimensional hexagonal reactor dynamic codes have been developed for VVER type reactors and coupled with different thermal
hydraulic system codes. In the EU Phare project SRR1/95 these codes have been validated against collected real plant transients by the participants from 7 countries. The two experiments chosen for calculation were such that both primary circuit behaviour and fission power behaviour were strongly affected including movements of control rods. Critical boron concentrations, 3-D core power distributions, time behaviour of fission power, coolant temperatures and pressures were the main parameters utilised in the validation. Good accuracy of the results was generally achieved comparable to the measurement accuracy. Confidence in the results of the different code systems has increased and the consequences of certain model changes could be evaluated.