On the fission gas release from oxide fuels during normal grain growth
Creators
- 1. Inst. for Nucl. Res., Pitesti (Romania)
- 2. Romanian Power Authority - Nuclear Power Group, B-dul Magheru, 33-35 Bucharest (Romania)
Description
A mathematical formalism for calculating the fission gas release from oxide fuels considering an arbitrary distribution of fuel grain size with only zero boundary condition for gas diffusion at the grain boundary is proposed. It has also been proved that it becomes unnecessary to consider the grain volume distribution function for fission products diffusion when the grain boundary gas resolution is considered, if thermodynamic forces on grain boundaries are only time dependent. In order to highlight the effect of the normal grain growth on fission gas release from oxide fuels Hillert's and Lifshitz and Slyozov's theories have been selected. The last one was used to give an adequate treatment of normal grain growth for the diffusion-controlled grain boundary movement in oxide fuels. It has been shown that during the fuel irradiation, the asymptotic form of the grain volume distribution functions given by Hillert and Lifshitz and Slyozov models can be maintained but the grain growth rate constant becomes time dependent itself. Experimental results have been used to correlate the two theoretical models of normal grain growth to the fission gas release from oxide fuels. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 246
- Journal Issue
- 2-3
- Journal Page Range
- p. 223-231.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 28064637
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BURNUP; DIFFUSION; FISSION PRODUCT RELEASE; GRAIN BOUNDARIES; GRAIN GROWTH; NUCLEAR FUELS; TEMPERATURE RANGE 1000-4000 K; THERMODYNAMICS; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CRYSTAL STRUCTURE; ENERGY SOURCES; FUELS; MATERIALS; MICROSTRUCTURE; OXIDES; OXYGEN COMPOUNDS; REACTOR MATERIALS; TEMPERATURE RANGE; URANIUM COMPOUNDS