Analisys of the NUPEC PSBT Tests With FLICA-OVAP Part 2: DNB Benchmark

Abstract

This paper discusses the results of a computational activity devoted to the prediction of boiling crisis phenomena. The capabilities of the FLICA-OVAP code have been tested against an extensive experimental database made available by the Japanese Nuclear Power Energy Corporation (NUPEC) in the frame of the PWR Subchannel and Bundle Tests (PSBT) international benchmark promoted by OECD and NRC. The experimental steady-state and transient tests herein addressed involve boiling crisis phenomena in rod bundles with uniform and non-uniform heat flux conditions. To some extent, the obtained results show good agreement between experimental data and calculations in many of the addressed conditions.