Interpretation of high-burnup fuel annealing tests
- 1. Paul Scherrer Institut, Villigen-PSI (Switzerland)
- 2. ENUSA Industrias Avanzadas, Madrid (ES)
- 3. Nordostschweizerische Kraftwerke AG (NOK) Kernenergie, Baden (CH)
Description
The growth of the porosity in high-burnup fuel is of particular interest when considering the effect of fission gas retention within the high-burnup structure (HBS). A mechanistic model of porosity growth under annealing conditions for light water reactor (LWR) UO2 fuel with typical stereological parameters of the HBS has been developed. The model takes into account both multipore and surface interactions that lead to fission gas release from the HBS porosity. We have applied the model to an HBS annealing experiment and found that reasonable agreement with the experimental gas release curve can be achieved for a vacancy diffusion enthalpy close to that measured experimentally. A comparison of the model behaviours at different pore growth rates is performed. We found that the model exhibits porosity evolution characteristics independent of the growth rate, specifically the existence of a maximum porosity, a continuous gas release, and a decreasing pore number density. A general comparison between the model results and in-pile data indicates that up to 250MWd/kgU, most of the gas is retained within the HBS. (author)
Additional details
Identifiers
- DOI
- 10.3327/jnst.45.639;
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 45
- Journal Issue
- 7
- Journal Page Range
- p. 639-646
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39106813
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANNEALING; BURNUP; DENSITY; DIFFUSION; ENTHALPY; FISSION PRODUCT RELEASE; GROWTH; MATHEMATICAL MODELS; MICROSTRUCTURE; NUCLEAR FUELS; POROSITY; TEMPERATURE RANGE 1000-4000 K; TIME DEPENDENCE; URANIUM DIOXIDE; VACANCIES; WATER COOLED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ENERGY SOURCES; FUELS; HEAT TREATMENTS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POINT DEFECTS; REACTOR MATERIALS; REACTORS; TEMPERATURE RANGE; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Available from doi: http://dx.doi.org/10.3327/jnst.45.639; 38 refs., 5 figs., 1 tab.