Analysis of fission gas release measurements using the COMETHE IIIJ and FCODE-Alpha computer codes. Final report
Description
Fission gas release predictions from FCODE-Alpha and COMETHE IIIJ were compared with experimental data from a representative group of light water reactor (LWR) fuel rods and with each other. In the first phase of the study, standard versions of the codes obtained from the Electric Power Software Center were compared with data from 36 rods. A modified version of COMETHE was used in the second phase of the study, which compared measurements from some of the same rods studied in the first phase, as well as with an additional 27 rods. Fission gas release predictions from both codes show substantial deviation from experimental measurements, and additional well-qualified data from LWR's is needed for comparison. Unpressurized rods experience significant degradation in heat transfer across the fuel-to-cladding gap as the lower thermal conductivity fission gases mix with the helium
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A05/MF A01.
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Additional details
Additional titles
- Augmented title (English)
- PWR; BWR
Publishing Information
- Imprint Pagination
- 77 p.
- Report number
- EPRI-NP--1954
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12638921
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTER CALCULATIONS; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL RODS; HEAT TRANSFER; POWER DENSITY; PWR TYPE REACTORS; RELIABILITY; THERMAL CONDUCTIVITY; THERMAL STRESSES
- Descriptors DEC
- ENERGY TRANSFER; FUEL ELEMENTS; ISOTOPES; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; STRESSES; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS