The solubility of selected fission products in UO2 and (U, Pu)O2
- 1 November 1993
- journal article
- other
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 206 (1) , 82-86
- https://doi.org/10.1016/0022-3115(93)90236-r
Abstract
No abstract availableThis publication has 21 references indexed in Scilit:
- The chemical state of the fission products in oxide fuelsPublished by Elsevier ,2003
- Microstructural change and its influence on fission gas release in high burnup UO2 fuelPublished by Elsevier ,2003
- High-temperature heat capacity of niobia-doped uranium oxideJournal of Nuclear Materials, 1992
- Post-irradiation examinations and composition of the residues from nitric acid dissolution experiments of high-burnup lwr fuelJournal of Nuclear Materials, 1990
- Phase equilibria in the pseudoquaternary BaO-UO2-ZrO2-MoO2 systemJournal of Nuclear Materials, 1987
- Solid solutions and phase equilibria in (U,Zr,Ln) oxides in the temperature range 1270–1670 KJournal of Nuclear Materials, 1981
- Post irradiation examination of simulated fission product doped hyperstoichiometric mixed oxide fuel pinsJournal of Nuclear Materials, 1980
- The chemical state of LWR high-power rods under irradiationJournal of Nuclear Materials, 1979
- Solubility and migration of fission product barium in oxide fuelJournal of Nuclear Materials, 1979
- Applications of thermodynamics for predicting and understanding the performance of fast breeder reactor oxide fuelsJournal of Nuclear Materials, 1974