Modelling of the fission product release from irradiated overheated LWR fuel
Description
This paper outlines the modelling work performed at BELGONUCLEAIRE in the frame of the COMETHE code, in order to describe the release of the fission products from LWR fuel, when the latter is overheated after operation at low temperature and high burnup. On basis of a review of high burnup data and power ramp tests, transient grain growth appears to be the most likely mechanism by which intragranular fission products can be transferred towards grain boundaries and fuel rod free volume; it also provides an evident interpretation of the denuded zones observed in irradiated fuel samples. A model is described where the grain growth rate is calculated as a function of fuel vapour pressure and grain boundary gas inventory. The main problem is to estimate the vapour pressure above irradiated fuel, as it results not only from the fuel, but also from the fuel-fission product compounds. Hence, grain growth and fission product release are expected to be quite sensitive to the irradiated fuel chemistry, stressing thus the need for the set-up of a comprehensive data base through ad-hoc international programmes. (author)
Additional details
Publishing Information
- Imprint Title
- Fuel rod internal chemistry and fission products behaviour
- Imprint Pagination
- 180 p.
- Journal Page Range
- p. 96-103.
- Report number
- IWGFPT--25
Conference
- Title
- Technical committee meeting on fuel rod internal chemistry and fission products behaviour.
- Dates
- 11-15 Nov 1985.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 18083044
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; C CODES; COMPUTERIZED SIMULATION; FISSION PRODUCT RELEASE; FUEL PELLETS; FUEL RODS; GASES; GRAIN GROWTH; PLUTONIUM DIOXIDE; PWR TYPE REACTORS; TRANSIENT OVERPOWER ACCIDENTS; URANIUM DIOXIDE; VERIFICATION
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ELEMENTS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 29 refs, 7 figs.