Considerations on the oxygen distribution in hypostoichiometric mixed oxide fuel pins
- 31 January 1974
- journal article
- other
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 49 (3) , 322-324
- https://doi.org/10.1016/0022-3115(74)90044-0
Abstract
No abstract availableKeywords
This publication has 5 references indexed in Scilit:
- Oxygen potential of irradiated urania-plutonia fuel pinsJournal of Nuclear Materials, 1973
- Mesures de resistivite et de cinetique d'oxydation dans PuO2−xJournal of Nuclear Materials, 1973
- MATERIAL TRANSPORT IN THE TEMPERATURE GRADIENT OF FAST REACTOR FUELSPublished by Elsevier ,1973
- Redistribution of plutonium and uranium in mixed (U, Pu) oxide fuel materials in a thermal gradientJournal of Nuclear Materials, 1971
- Thermal diffusion in closed oxide fuel systemsJournal of Nuclear Materials, 1969