A model for evolution of oxygen potential and stoichiometry deviation in irradiated UO2 fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference36 articles.
1. Fission product release from trace irradiated UO2+x
2. Effect of stoichiometry on diffusion of xenon in UO2
3. Gas release mechanisms in UO2—a critical review
4. Thermal conductivity of hyperstoichiometric SIMFUEL
5. The chemical state of the fission products in oxide fuels
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3. Simulation of radioactive fission gas release from defective PWR fuel rod using the MFPR/R mechanistic code;Journal of Nuclear Materials;2023-09
4. Modeling and simulation of oxygen transport in high burnup LWR fuel;Journal of Nuclear Materials;2020-09
5. Oxygen potential calculations for conventional and Cr-doped UO2 fuels based on solid solution thermodynamics;Journal of Nuclear Materials;2020-06
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