The transfer of fission gas between grain faces and edges in UO2
- 31 August 1978
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 75 (2) , 282-287
- https://doi.org/10.1016/0022-3115(78)90009-0
Abstract
No abstract availableKeywords
This publication has 6 references indexed in Scilit:
- The spacing of intergranular fission gas bubbles in irradiated UO2Journal of Nuclear Materials, 1978
- Swelling and gas release in UO2 at low and intermediate temperaturesJournal of Nuclear Materials, 1977
- Vacancy Potential and Void Growth on Grain BoundariesMetal Science, 1975
- Swelling in UO2under conditions of gas releasePhilosophical Magazine, 1974
- The effect of grain size on the swelling and gas release properties of uo2 during irradiationJournal of Nuclear Materials, 1974
- Examination of neutron-irradiated UO2 using the scanning electron microscopeJournal of Materials Science, 1970