First-principles analysis of intergranular fracture in UN by Σ5(210) grain boundary segregated Xe and vacancy
Author:
Funder
National Natural Science Foundation of China
Publisher
Elsevier BV
Reference28 articles.
1. Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium mononitride;Watkins;J. Nucl. Mater.,2021
2. Steam oxidation of uranium mononitride in pure and reducing steam atmospheres to 1200 °C;Sooby;J. Nucl. Mater.,2022
3. Oxidation susceptibility of UN Σ5(210) grain boundary with Al/Cr/Ni dopant: a first-principles study;Wang;J. Nucl. Mater.,2023
4. Irradiation effects on the fracture properties of UO2 fuels studied by micro-mechanical testing;Henry;J. Nucl. Mater.,2020
5. Radiation stability of uranium mononitride;Wullaert;Battelle Memorial Inst., Columbus,1963
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