Void Fraction Prediction by CATHARE 2 of OECD/NRC BFBT and PSBT Benchmarks

Abstract

The objective of the current study is to evaluate the performance of the last version of the French best estimate thermal-hydraulic code CATHARE 2 regarding void fraction prediction, comparing the analytical results with the experiments in the framework of International OECD/NRC Benchmarks based on NUPEC (Nuclear Power Engineering Corporation) BWR Full-size Fine-mesh Bundle Tests (BFBT) and PWR Subchannel and Bundle Tests (PSBT). The results show reasonable prediction of the void fraction distribution in broad range of variation of the operational parameters: pressures, mass fluxes, power and inlet subcooling, which characterize the operation of Light Water Reactors.