Evaluation of ASSERT-PV V3R1 against the PSBT Benchmark
Creators
- 1. Department of Engineering Physics, McMaster University, 1280 Main Street West, Hamilton, ON, Canada L8S 4L7
Description
Void fraction and DNB calculations conducted using ASSERT-PV V3R1 are evaluated against data from the NUPEC database as part of the OECD/NEA Pressurized Water Reactor Subchannel Benchmark Tests (PSBT). Void fraction measurements were well represented in the isolated single subchannel cases, with 77.0% of all predicted values falling withinof the experimental value. In the B5 type bundle, an average void fraction error ofwas reported at the lower elevation, while this value wasat the upper measurement location. ASSERT was able to predict the steady state DNB power of the bundles to within ±10% of the measured value for a total of 344 times out of 432. Sensitivity studies conducted indicate that the Ahmad correlation with the Groeneveld 1995 CHF lookup table yielded the most accurate results, although some data points fell within the limiting quality region where the accuracy was reduced.
Files
10.1155_2012_863503.pdf
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Additional details
Identifiers
- DOI
- 10.1155/2012/863503;
Publishing Information
- Journal Title
- Science and Technology of Nuclear Installations
- Journal Volume
- 2012
- Journal Page Range
- 1-21
- ISSN
- 1687-6075
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- ACCURACY; BENCHMARKS; CORRELATIONS; CRITICAL HEAT FLUX; DATA BASE MANAGEMENT; DEPARTURE NUCLEATE BOILING; ERRORS; EVALUATION; FUEL ELEMENT CLUSTERS; LEVELS; NEA; PWR TYPE REACTORS; SENSITIVITY ANALYSIS; STEADY-STATE CONDITIONS; VOID FRACTION; VOIDS
- Descriptors DEC
- BOILING; ENRICHED URANIUM REACTORS; FUEL ASSEMBLIES; HEAT FLUX; INTERNATIONAL ORGANIZATIONS; MANAGEMENT; NUCLEATE BOILING; OECD; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- © Author(s)
- Notes
- Record automatically processed