Modelling of grain face bubbles coalescence in irradiated UO2 fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference22 articles.
1. Thermal treatment of uranium oxide irradiated in pressurized water reactor: Swelling and release of fission gases
2. A.V. Berdyshev, M.S. Veshchunov, Modelling of Grain Face Diffusion Transport and Swelling in UO2 Fuel, Preprint IBRAE-2002-14, Moscow, 2002.
3. Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel
4. Migration of Macroscopic Precipitates in Solid Materials;Geguzin,1971
5. The development of grain-face porosity in irradiated oxide fuel
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