Cobra-IE Evaluation by Simulation of the NUPEC BWR Full-Size Fine-Mesh Bundle Test (BFBT)
The COBRA-IE computer code is a thermal-hydraulic subchannel analysis program capable of simulating phenomena present in both PWRs and BWRs. As part of ongoing COBRA-IE assessment efforts, the code has been evaluated against experimental data from the NUPEC BWR Full-Size Fine-Mesh Bundle Tests (BFBT). The BFBT experiments utilized an 8 x 8 rod bundle to simulate BWR operating conditions and power profiles, providing an excellent database for investigation of the capabilities of the code. Benchmarks performed included steady-state and transient void distribution, single-phase and two-phase pressure drop, and steady-state and transient critical power measurements. COBRA-IE effectively captured the trends seen in the experimental data with acceptable prediction error. Future sensitivity studies are planned to investigate the effects of enabling and/or modifying optional code models dealing with void drift, turbulent mixing, rewetting, and CHF.
- Research Organization:
- Bettis Atomic Power Laboratory (BAPL), West Mifflin, PA
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- DE-AC11-98PN38206
- OSTI ID:
- 923318
- Report Number(s):
- B-T-3653; TRN: US0801807
- Resource Relation:
- Conference: OECD/NRC Benchmark based on NUPEC BWR Full-size Fine-mesh Bundle Tersts (BFBT) - Third Workshop (BFBT-3), Pisa, Italy, 04/26/2006 - 04/28/2006
- Country of Publication:
- United States
- Language:
- English
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