Analisys of the NUPEC PSBT Tests With FLICA-OVAP Part 2: DNB Benchmark
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
O8-3 OECD Thermalhydraulics Benchmarks

Matteo Bucci (CEA Saclay)
Philippe Fillion (CEA Saclay)


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.

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