The kinetics of fission gas venting from saturated grain boundaries in irradiated UO2
Description
The kinetics of fission gas release from post-irradiation annealed UO2 has been analysed using the stand-alone version of the ENIGMA fission gas release model. This model calculates the arrival rate of fission gas to grain boundaries under circumstances where there is a competition between migration to grain boundaries and absorption by and emission from a coarsening population of intragranular bubbles. The fraction of the fission gas vented from the boundaries is critically dependent on the temperature ramp rate and for low ramp rates there is insignificant gas release until the grain boundary concentration reaches a critical value. The subsequent evolution of gas from the saturated boundaries is consistent with a grain boundary model based on a quasi-crystalline treatment of the lenticular grain face bubbles. At higher ramp rates the entire inventory of the grain boundaries is vented and there appears to be a critical temperature dependent threshold between normal incubation and total venting. (author)
Additional details
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (United Kingdom)
- ISBN
- 0 7277 2033 3
- Imprint Title
- Fuel management and handling. Proceedings
- Imprint Pagination
- 368 p.
- Journal Page Range
- p. 218-226.
Conference
- Title
- International conference on fuel management and handling.
- Dates
- 20-22 Mar 1995.
- Place
- Edinburgh (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 28050200
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ANNEALING; BUBBLES; COMPUTERIZED SIMULATION; E CODES; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; GASES; GRAIN BOUNDARIES; KINETICS; MATHEMATICAL MODELS; POST-IRRADIATION EXAMINATION; SPENT FUELS; THEORETICAL DATA; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; COMPUTER CODES; CRYSTAL STRUCTURE; DATA; ENERGY SOURCES; FLUIDS; FUELS; HEAT TREATMENTS; INFORMATION; MATERIALS; MICROSTRUCTURE; NUCLEAR FUELS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SIMULATION; URANIUM COMPOUNDS; URANIUM OXIDES