Modelling intragranular fission gas release in irradiation of sintered LWR UO2 fuel
- 31 July 2002
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 304 (1) , 29-49
- https://doi.org/10.1016/s0022-3115(02)00856-5
Abstract
No abstract availableKeywords
This publication has 41 references indexed in Scilit:
- A new fission-gas release modelPublished by Elsevier ,2003
- High resolution TEM of high burnup UO2 fuelJournal of Nuclear Materials, 1997
- Transmission electron microscopy study of fission product behaviour in high burnup UO2Journal of Nuclear Materials, 1992
- On diffusion and precipitation of gas-in-solidJournal of Nuclear Materials, 1987
- Fission product release from nuclear fuel by recoil and knockoutJournal of Nuclear Materials, 1987
- Recoil release of fission products from nuclear fuelJournal of Nuclear Materials, 1985
- Diffusion theory of fission gas migration in irradiated nuclear fuel UO2Journal of Nuclear Materials, 1985
- Approximate treatment of the grain-boundary loss term in fission gas release modelsJournal of Nuclear Materials, 1981
- The fission gas bubble distribution in uranium dioxide from high temperature irradiated sghwr fuel pinsJournal of Nuclear Materials, 1977
- The nucleation of bubbles and re-solution effects in uranium dioxide irradiated at elevated temperaturesJournal of Nuclear Materials, 1971