Modelling of fission gas spatial distribution in single grains of UO2 fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference10 articles.
1. Fission gas and caesium gradients in single grains of transient tested UO2 fuel: Results of an EPMA investigation
2. Modelling of inert gas bubble behaviour during annealing of irradiated molybdenum
3. Fission gas bubble behaviour in uranium dioxide
4. Gas release and swelling in oxide fuel; modeling of the kinetics of gas porosity development
Cited by 3 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Modelling intra-granular bubble movement and fission gas release during post-irradiation annealing of UO2 using a meso-scale and spatialized approach;Journal of Nuclear Materials;2020-01
2. Inert gas release from metals and UO2 during high temperature annealing: the role of thermal vacancies;Journal of Nuclear Materials;1995-08
3. Bubble diffusion to grain boundaries in UO2 and metals during annealing: a new approach;Journal of Nuclear Materials;1994-06
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