Behaviour of fission gas products in single crystal UO2 during intermediate temperature irradiation
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference24 articles.
1. Calculations on the in-pile behavior of fission gas in oxide fuels
2. J. M. Griesmayer and N. M. Ghoniem, USNRC Report NUREG/CR-0906.
3. A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation
4. Release of Fission Gas During Fissioning of UO2
5. A Dynamic Method for In-Pile Fission-Gas Release Studies
Cited by 5 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. Formation of Nanostructures in UO2Fuel at High Burn-ups;Acta Physica Polonica A;2002-08
2. Modification of Recrystallization Temperature of Uranium Dioxide in Function of Burn-Up and Its Impact on Fission Gas Release;Acta Physica Polonica A;1999-07
3. Influence of Thin Surface Layer on Fission Gas Release from Uranium Dioxide Single Crystal during Irradiation;Acta Physica Polonica A;1996-03
4. The diffusion coefficient of fission-product rare gases in single crystal uranium dioxide during irradiation;Journal of Nuclear Materials;1994-06
5. Gas-leaking fuel elements number and fission gas product coolant volumetric activities assessment in the VVER-440 nuclear power plant;Journal of Nuclear Materials;1992-07
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