Published 2007 | Version v1
Miscellaneous

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)

Part of:
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference

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.