Comparative analysis of swelling and porosity evolution in UO fuel via two approaches
Creators
- 1. Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of)
Description
A correlation for the volume porosity of irradiated UO fuel as a sum of the individual contributions of the pore and swelling porosity in terms of the local density and fractional matrix swelling is developed. By using the existing low temperature low burnup model of swelling, evolution of the matrix swelling and porosity terms are calculated for UO fuel in the low burnup but in the high burnup two various models are applied, the one with considering grain recrystallization and another without it but with the method of Xe depletion measurement. The purpose of the paper is comparison of fuel swelling behavior between two models at high burnups. The bulk swelling and porosity evolution in both methods are also validated by experimental data. Finally, one conclusion from this comparison is obtained, as the method which considering grain recrystallization has more rational behavior in the fuel swelling and porosity.
Availability note (English)
Available from: http://dx.doi.org/10.1515/kern-2022-0121Additional details
Identifiers
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 88
- Journal Issue
- 3
- Journal Page Range
- p. 354-360
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 54096911
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BURNUP; NUCLEAR FUELS; POROSITY; RECRYSTALLIZATION; SWELLING; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DEFORMATION; ENERGY SOURCES; FUELS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; URANIUM COMPOUNDS; URANIUM OXIDES