Thermodynamic calculations of oxygen self-diffusion in mixed-oxide nuclear fuels [electronic resource].
- Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2016. and Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy
- Physical Description:
- pages 74,018-74,027 : digital, PDF file
- Additional Creators:
- Los Alamos National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Mixed-oxide fuels containing uranium with thorium and/or plutonium may play an important part in future nuclear fuel cycles. There are, however, significantly less data available for these materials than conventional uranium dioxide fuel. In the present study, we employ molecular dynamics calculations to simulate the elastic properties and thermal expansivity of a range of mixed oxide compositions. These are then used to support equations of state and oxygen self-diffusion models to provide a self-consistent prediction of the behaviour of these mixed oxide fuels at arbitrary compositions.
- Published through SciTech Connect., 07/29/2016., "la-ur-16-23378", RSC Advances 6 78 ISSN 2046-2069 (Electronic) AM, and David C. Parfitt; Michael William Cooper; Michael J.D. Rushton; S. R. Christopoulos; M. E. Fitzpatrick; A. Chroneos.
- Funding Information:
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