The effect of additives on the irradiation behaviour of UO2
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference14 articles.
1. A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation
2. The release of fission gas from nuclear fuels during temperature transients
3. Effect of stoichiometry on diffusion of xenon in UO2
4. Das system UO2UO3LaO1.5
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2. Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2;Journal of Nuclear Materials;2024-06
3. Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives;Nuclear Engineering and Design;2023-08
4. Diffusion in undoped and Cr-doped amorphous UO2;Journal of Nuclear Materials;2023-04
5. Prospects for additive manufacturing of nuclear fuel forms;Progress in Nuclear Energy;2023-01
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