Redistribution of plutonium and uranium in mixed (U, Pu) oxide fuel materials in a thermal gradient
- 30 June 1971
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 39 (3), 265-284
- https://doi.org/10.1016/0022-3115(71)90146-2
Abstract
No abstract availableKeywords
This publication has 8 references indexed in Scilit:
- High temperature studies of Urania in a thermal gradientJournal of Nuclear Materials, 1969
- Oxygen and uranium diffusion in uranium dioxide (a review)Journal of Nuclear Materials, 1969
- Kinetics of diffusional motion of pores in solidsJournal of Nuclear Materials, 1969
- Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron fluxJournal of Nuclear Materials, 1969
- Thermal diffusion in nuclear reactor fuelsJournal of the American Chemical Society, 1968
- Thermodiffusion im system UO2CeO2Journal of Nuclear Materials, 1967
- Diffusion of Pu in U02Radiochimica Acta, 1963
- Thermodiffusion und Überführungswärme in kondensierten PhasenThe European Physical Journal A, 1948