Thermomigration of oxygen in (U, Pu)O2−x described by a cluster model
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference19 articles.
1. MATERIAL TRANSPORT IN THE TEMPERATURE GRADIENT OF FAST REACTOR FUELS
2. Effect of a temperature gradient on the stoichiometry of urania-plutonia fuel
3. Redistribution of plutonium and uranium in mixed (U, Pu) oxide fuel materials in a thermal gradient
4. Thermodynamics of Nuclear Materials 1974;Sari,1975
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1. Cation interdiffusion in uranium–plutonium mixed oxide fuels: Where are we now?;Frontiers in Nuclear Engineering;2022-12-09
2. Thermal diffusion and Soret effect in (U,Me)O2+δ: the heat of transport of oxygen;Journal of Nuclear Materials;1998-06
3. Safety aspects of fuel behaviour during faults and accidents in pressurised water reactors and in liquid sodium cooled fast breeder reactors;Journal of Nuclear Materials;1989-07
4. Thermomigration in (UCe)O2−x;Journal of Nuclear Materials;1985-10
5. Solid phase thermal diffusion as a mechanism for oxygen redistribution in UO2 ± x and (U, Pu)O2±x;Journal of Nuclear Materials;1981-03
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