Abstract
In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer Institut has participated in the OECD/NRC PSBT benchmark with the thermal-hydraulic system code TRACE5.0 developed by US NRC, the subchannel code FLICA4 developed by CEA, and the computational fluid dynamic code STAR-CD developed by CD-adapco. The PSBT benchmark consists of a series of void distribution exercises and departure from nucleate boiling exercises. The results reveal that the prediction by the subchannel code FLICA4 agrees with the experimental data reasonably well in both steady-state and transient conditions. The analyses of single-subchannel experiments by means of the computational fluid dynamic code STAR-CD with the CD-adapco boiling model indicate that the prediction of the void fraction has no significant discrepancy from the experiments. The analyses with TRACE point out the necessity to perform additional assessment of the subcooled boiling model and bulk condensation model of TRACE.
Highlights
An international benchmark program, namely, the OECD/ NRC NUPEC BWR Full-Size Bundle Test (BFBT) Benchmark [1], was organized by OECD/NEA and US NRC to encourage advancement in subchannel analysis methods
In order to assess the accuracy and validity of subchannel, system, and computational fluid dynamics codes, the Paul Scherrer Institut has participated in the OECD/NRC PWR subchannel and bundle tests (PSBT) benchmark with the thermal-hydraulic system code TRACE5.0 developed by US NRC, the subchannel code FLICA4 developed by CEA, and the computational fluid dynamic code STAR-CD developed by CD-adapco
The results indicate that FLICA4 predicts departure from nucleate boiling (DNB) earlier than in the experiment
Summary
The OECD/ NRC NUPEC BWR Full-Size Bundle Test (BFBT) Benchmark [1], was organized by OECD/NEA and US NRC to encourage advancement in subchannel analysis methods. About 30 organizations from 15 countries had participated in the benchmark and an extensive validation of subchannel, computational fluid dynamic (CFD), and thermal hydraulic system codes had been carried out. Building on the success of the BFBT benchmark, OECD/NEA and US NRC have organized an additional international benchmark program for pressurized water reactor (PWR) conditions [2]. The application of CFD for subchannel analysis is considered as the new frontier of the state-of-the-art methodologies. In this context, PSI decided to participate in the PSBT benchmark with FLICA4 and a commercial CFD code, namely, STARCD [4]. This paper reviews the different analyses of the PSBT Benchmark that were conducted at PSI, and discusses and compares the results obtained with the different thermal hydraulic codes
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