Creep properties of oxide and carbide fuels under irradiation
- 31 March 1977
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 65, 24-36
- https://doi.org/10.1016/0022-3115(77)90038-1
Abstract
No abstract availableKeywords
This publication has 2 references indexed in Scilit:
- A model for in-reactor densification of UO2Philosophical Magazine, 1975
- Fission-enhanced self-diffusion of uranium in UO2 and UCJournal of Nuclear Materials, 1973