The effect of lattice and grain boundary diffusion on the redistribution of Xe in metallic nuclear fuels: Implications for the use of ion implantation to study fission-gas-bubble nucleation mechanisms
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference53 articles.
1. An analytical study of gas-bubble nucleation mechanisms in uranium-alloy nuclear fuel at high temperature
2. The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile material
3. The distribution of intragranular fission gas bubbles in UO2 during irradiation
4. Segregation of alloying elements to free surfaces during irradiation
5. Ion-irradiation studies of the damage function of copper and silver
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1. Evidence of Xe-incorporation in the bubble superlattice in irradiated U-Mo fuel;Journal of Nuclear Materials;2023-12
2. TEM and XAS investigation of fission gas behaviors in U-Mo alloy fuels through ion beam irradiation;Journal of Nuclear Materials;2017-10
3. Heavy ion linear accelerator for radiation damage studies of materials;Review of Scientific Instruments;2017-03
4. Defect evolution in a NiMoCrFe alloy subjected to high-dose Kr ion irradiation at elevated temperature;Journal of Nuclear Materials;2016-06
5. Thin uranium dioxide films with embedded xenon;Journal of Nuclear Materials;2013-06
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