Light water reactor fuel rod modeling code evaluation. Phase II topical report
Description
Several fuel performance modeling codes have been developed throughout the industry over the last ten years for use in predicting fuel rod behavior. Three of these codes (BEHAVE-4, FMODEL, and LIFE-III) were developed originally for fast breeder reactor (FBR) analysis and have been converted for light water reactor (LWR) analysis as a part of the contract work. Three other codes (COMETHE, CYGRO-3, and GAPCON-THERMAL-1) were developed originally for LWR analysis and, therefore, required no conversion. Code predictions of fuel central temperatures, fission gas release, cladding strains, internal rod gas pressures, cold diametral gaps and fuel pellet central void radii are provided for four experimental and one commercial fuel rod. An evaluation of the codes is included, based on their predictability of the experimental data available for the rods
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A08/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 163 p.
- Report number
- CENPD--218
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9379620
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; COMPUTER CODES; FISSION PRODUCT RELEASE; FUEL RODS; HEAT TRANSFER; PERFORMANCE; POWER DISTRIBUTION; PWR TYPE REACTORS; SPATIAL DISTRIBUTION; STRESS ANALYSIS
- Descriptors DEC
- DISTRIBUTION; ENERGY TRANSFER; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS