Published February 1981
| Version v1
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Fission gas release from oxide fuels at high burnups (AWBA development program)
Description
The steady state gas release, swelling and densification model previously developed for oxide fuels has been modified to accommodate the slow transients in temperature, temperature gradient, fission rate and pressure that are encountered in normal reactor operation. The gas release predictions made by the model were then compared to gas release data on LMFBR-EBRII fuels obtained by Dutt and Baker and reported by Meyer, Beyer, and Voglewede. Good agreement between the model and the data was found. A comparison between the model and three other sets of gas release data is also shown, again with good agreement
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- WAPD-TM--1443
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12608411
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BURNUP; FISSION PRODUCT RELEASE; FUEL RODS; LWBR TYPE REACTORS; PHYSICAL RADIATION EFFECTS; SWELLING; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; DEFORMATION; FUEL ELEMENTS; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS