Migration of fission product barium in UO2 fuel under transient conditions
- 1 September 1990
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 173 (1) , 14-25
- https://doi.org/10.1016/0022-3115(90)90308-a
Abstract
No abstract availableKeywords
This publication has 8 references indexed in Scilit:
- The chemical state of the fission products in oxide fuelsPublished by Elsevier ,2003
- Concerning the development of grain face bubbles and fission gas release in UO2 fuelJournal of Nuclear Materials, 1988
- Phase equilibria in the pseudoquaternary BaO-UO2-ZrO2-MoO2 systemJournal of Nuclear Materials, 1987
- On the rate determining step in fission gas release from high burn-up water reactor fuel during power transientsJournal of Nuclear Materials, 1987
- Fission Product Behavior in High-Burnup Water Reactor Fuel Subjected to Slow Power IncreasesNuclear Technology, 1986
- Local fission gas release and swelling in water reactor fuel during slow power transientsJournal of Nuclear Materials, 1985
- FIPMIGR — A computer program for studying migration of fission products in a temperature gradientNuclear Engineering and Design, 1980
- Solubility and migration of fission product barium in oxide fuelJournal of Nuclear Materials, 1979