Benchmarking and qualification of the nufreq-npw code for best estimate prediction of multi-channel core stability margins
- 1. Westinghouse Commercial Nuclear Fuel Div., Pittsburgh, PA (USA)
- 2. Rensselear Polytechnic Inst., Troy, NY (USA)
Description
The work described in this paper is focused on the development, verification and benchmarking of the NUFREQ-NPW code at Westinghouse, USA for best estimate prediction of multi-channel core stability margins in US BWRs. Various models incorporated into NUFREQ-NPW are systematically compared against the Westinghouse channel stability analysis code MAZDA, which the Mathematical Model was developed in an entirely different manner. The NUFREQ-NPW code is extensively benchmarked against experimental stability data with and without nuclear reactivity feedback. Detailed comparisons are next performed against nuclear-coupled core stability data. A physically based algorithm is developed to correct for the effect of flow development on subcooled boiling. Use of this algorithm (to be described in the full paper) captures the peak magnitude as well as the resonance frequency with good accuracy
Additional details
Publishing Information
- Publisher
- Clean Energy Research Inst. University of Miami.
- Imprint Place
- Coral Gables, FL (USA)
- Imprint Title
- The 5th Miami international symposium on multi-phase transport and particulate phenomena (Condensed Papers)
- Imprint Pagination
- 181 p.
- Journal Page Range
- p. 44-46.
Conference
- Title
- 5. Miami international symposium on multi-phase transport and particulate phenomena.
- Dates
- 12-14 Dec 1988.
- Place
- Miami Beach, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21006530
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; FLOW MODELS; FUEL CHANNELS; HYDRAULICS; N CODES; REACTOR SAFETY; STABILITY
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; MATHEMATICAL MODELS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-881202--.