EXPERIMENTAL VERIFICATION OF THE THREE-DIMENSIONAL THERMAL-HYDRAULIC MODELS IN THE BEST-ESTIMATE CODE BAGIRA.
Conference
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OSTI ID:15007781
In this paper we present verification results of the BAGIRA code that was performed using data from integral thermal-hydraulic experimental test facilities as well as data obtained from operating nuclear power plants. BAGIRA is a three-dimensional numerical best-estimate code that includes non-homogeneous modeling. Special consideration was given to the recently completed experimental data from the PSB-VVER integral test facility (EREC, Electrogorsk, Russia)--a new Russian large-scale four-loop unit, which has been designed to model the primary circuits of VVER-1000 type reactors. It is demonstrated that the code BAGIRA can be used to analyze nuclear reactor behavior under normal and accident conditions.
- Research Organization:
- BROOKHAVEN NATIONAL LABORATORY (US)
- Sponsoring Organization:
- DOE/NNSA (US)
- DOE Contract Number:
- AC02-98CH10886
- OSTI ID:
- 15007781
- Report Number(s):
- BNL--72239-2004-CP; NN-410-1010
- Country of Publication:
- United States
- Language:
- English
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