tThis paper presents an application of the French best estimate thermal-hydraulic code CATHARE 2 tocalculate the critical power and departure from nucleate boiling (DNB) exercises of the InternationalOECD/NRC BWR Fuel Bundle Test (BFBT) benchmark. The assessment activity is performed comparingthe code calculation results with available in the framework of the benchmark experimental data fromJapanese Nuclear Power Engineering Corporation (NUPEC).Two-phase flow calculations on prediction of the critical power have been carried out both in steadystate and transient cases, using one-dimensional and three-dimensional modelling. Results of the steady-state critical power tests calculation have shown the ability of CATHARE code to predict reasonably thecritical power and its location, using appropriate modelling.

Critical power prediction by CATHARE2 of the OECD/NRC BFBT benchmark

D'AURIA, FRANCESCO SAVERIO
2015

Abstract

tThis paper presents an application of the French best estimate thermal-hydraulic code CATHARE 2 tocalculate the critical power and departure from nucleate boiling (DNB) exercises of the InternationalOECD/NRC BWR Fuel Bundle Test (BFBT) benchmark. The assessment activity is performed comparingthe code calculation results with available in the framework of the benchmark experimental data fromJapanese Nuclear Power Engineering Corporation (NUPEC).Two-phase flow calculations on prediction of the critical power have been carried out both in steadystate and transient cases, using one-dimensional and three-dimensional modelling. Results of the steady-state critical power tests calculation have shown the ability of CATHARE code to predict reasonably thecritical power and its location, using appropriate modelling.
Lutsanych, S.; Sabotinov, L.; D'Auria, FRANCESCO SAVERIO
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/11568/835738
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