Application of lattice constant measurements for stoichiometry determination in irradiated U-Pu mixed oxide fuels
- 30 September 1971
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 40 (3), 325-337
- https://doi.org/10.1016/0022-3115(71)90100-0
Abstract
No abstract availableKeywords
This publication has 6 references indexed in Scilit:
- Solid fission product behavior in uranium-plutonium oxide fuel irradiated in a fast neutron fluxJournal of Nuclear Materials, 1969
- Etude de la conductibilite thermique des oxydes mixtes d'uranium et de plutoniumJournal of Nuclear Materials, 1968
- The uranium-plutonium-oxygen ternary phase diagramJournal of Inorganic and Nuclear Chemistry, 1967
- Fission product effects in uranium dioxideJournal of Nuclear Materials, 1963
- Radiation Self-Damage in Plutonium CompoundsNature, 1962
- On the Chemistry of the Fission Process in Reactor Fuels Containing UF4and UO2Nuclear Science and Engineering, 1958