Multiscale simulation of xenon diffusion and grain boundary segregation in UO2
Creators
- 1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- 2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
In light water reactor fuel, gaseous fission products segregate to grain boundaries, resulting in the nucleation and growth of large intergranular fission gas bubbles. The segregation rate is controlled by diffusion of fission gas atoms through the grains and interaction with the boundaries. Based on the mechanisms established from earlier density functional theory (DFT) and empirical potential calculations, diffusion models for xenon (Xe), uranium (U) vacancies and U interstitials in UO2 have been derived for both intrinsic (no irradiation) and irradiation conditions. Segregation of Xe to grain boundaries is described by combining the bulk diffusion model with a model for the interaction between Xe atoms and three different grain boundaries in UO2 (Sigma 5 tilt, Sigma 5 twist and a high angle random boundary), as derived from atomistic calculations. The present model does not attempt to capture nucleation or growth of fission gas bubbles at the grain boundaries. The point defect and Xe diffusion and segregation models are implemented in the MARMOT phase field code, which is used to calculate effective Xe and U diffusivities as well as to simulate Xe redistribution for a few simple microstructures
Availability note (English)
Available from: DOI:10.1016/j.jnucmat.2015.03.019 ; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo period from OSTI using http://www.osti.gov/pages/biblio/1193643Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 462
- Journal Issue
- C
- Journal Page Range
- p. 15-25
- ISSN
- 0022-3115
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- United States
- INIS RN
- 47051984
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- DENSITY FUNCTIONAL METHOD; FISSION PRODUCTS; GASEOUS DIFFUSION; GRAIN BOUNDARIES; SIMULATION; URANIUM; URANIUM DIOXIDE; WATER COOLED REACTORS; WATER MODERATED REACTORS; XENON
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CALCULATION METHODS; CHALCOGENIDES; DIFFUSION; ELEMENTS; FLUIDS; GASES; ISOTOPES; MATERIALS; METALS; MICROSTRUCTURE; NONMETALS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RARE GASES; REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; VARIATIONAL METHODS
Optional Information
- Funding organization
- USDOE (United States)
- Secondary number(s)
- INL/JOU--15-35649; OSTIID--1193643