Impact of thermal conductivity models on the coupling of heat transport and oxygen diffusion in UO2 nuclear fuel elements
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference34 articles.
1. A review of nuclear fuel performance codes
2. Computer models for fuel element behaviour
3. An object-oriented finite element framework for multiphysics phase field simulations
4. Numerical verification of equilibrium thermodynamic computations in nuclear fuel performance codes
5. Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2Fuels
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