Diffusion of oxygen interstitials in UO2+x using kinetic Monte Carlo simulations: Role of O/M ratio and sensitivity analysis
Creators
- 1. Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States)
- 2. School of Chemical & Biomolecular Engineering, Georgia Institute of Technology, Atlanta, GA 30332 (United States)
- 3. Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)
Description
Oxygen interstitials in UO2+x significantly affect the thermophysical properties and microstructural evolution of the oxide nuclear fuel. In hyperstoichiometric Urania (UO2+x), these oxygen interstitials form different types of defect clusters, which have different migration behavior. In this study we have used kinetic Monte Carlo (kMC) to evaluate diffusivities of oxygen interstitials accounting for mono- and di-interstitial clusters. Our results indicate that the predicted diffusivities increase significantly at higher non-stoichiometry (x > 0.01) for di-interstitial clusters compared to a mono-interstitial only model. The diffusivities calculated at higher temperatures compare better with experimental values than at lower temperatures (< 973 K). We have discussed the resulting activation energies achieved for diffusion with all the mono- and di-interstitial models. We have carefully performed sensitivity analysis to estimate the effect of input di-interstitial binding energies on the predicted diffusivities and activation energies. While this article only discusses mono- and di-interstitials in evaluating oxygen diffusion response in UO2+x, future improvements to the model will primarily focus on including energetic definitions of larger stable interstitial clusters reported in the literature. The addition of larger clusters to the kMC model is expected to improve the comparison of oxygen transport in UO2+x with experiment.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2016.02.003Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2016.02.003;
- PII
- S0022-3115(16)30044-7;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 472
- Journal Page Range
- p. 89-98
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48034860
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ACTIVATION ENERGY; BINDING ENERGY; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DEFECTS; DENSITY FUNCTIONAL METHOD; DIFFUSION; INTERSTITIALS; MICROSTRUCTURE; MIGRATION; MONTE CARLO METHOD; NUCLEAR FUELS; OXYGEN; SENSITIVITY ANALYSIS; STOICHIOMETRY; TEMPERATURE RANGE 0400-1000 K; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTS; ENERGY; ENERGY SOURCES; EVALUATION; FUELS; MATERIALS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; POINT DEFECTS; REACTOR MATERIALS; SIMULATION; TEMPERATURE RANGE; URANIUM COMPOUNDS; URANIUM OXIDES; VARIATIONAL METHODS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.