Development of a reduced oxidation model for hyperstoihiometric UO2+x
Creators
- 1. Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)
Description
A numerical treatment was developed for predicting fuel oxidation in uranium-dioxide fuel, using a system of two time-dependent partial differential equations for hyperstoichiometry and temperature. This model was developed as a simplification from a previous mechanistic treatment, against which the current treatment is benchmarked, that also includes equations for hydrogen and steam transport in the fuel-to-sheath gap and fuel cracks. These factors were addressed in the reduced treatment using semi-empirical correlations to increase the model's robustness and computational speed. Further work has involved testing the model against experimental data available from coulometric titration experiments performed at the Chalk River Laboratories. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-88-7
- Imprint Title
- Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference
- Imprint Pagination
- 303 Megabytes
- Journal Page Range
- [12 p.]
Conference
- Title
- Canada's nuclear renewal and growth
- Acronym
- 28. Annual conference of the Canadian Nuclear Society and 31. CNS/CNA student conference on embracing the future
- Dates
- 3-6 Jun 2007
- Place
- Saint John, New Brunswick (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 38107490
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACKS; FUEL CANS; HYDROGEN; NUCLEAR FUELS; OXIDATION; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; ELEMENTS; ENERGY SOURCES; FUELS; MATERIALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; SIMULATION; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Paper S2008; 6 refs., 1 tab., 9 figs.