The effect of cladding restraint on fission gas release behavior
- 1 August 1988
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 158, 64-70
- https://doi.org/10.1016/0022-3115(88)90155-9
Abstract
No abstract availableThis publication has 9 references indexed in Scilit:
- Fission gas release from power-ramped UO2 fuelJournal of Nuclear Materials, 1986
- Finite element model for analysis of fission gas release from UO2 fuel.Journal of Nuclear Science and Technology, 1985
- Transiente spaltgasfreisetzung und UO2-mikrostruktur bei leistungsrampenJournal of Nuclear Materials, 1984
- Diffusional growth of overpressured fission-gas bubbles on grain boundariesJournal of Nuclear Materials, 1982
- In-Pile Diameter Measurement of Light Water Reactor Test Fuel Rods for Assessment of Pellet-Cladding Mechanical InteractionNuclear Technology, 1980
- 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
- Internal Gas Pressure Behavior in Mixed-Oxide Fuel Rods Fuels During IrradiationNuclear Applications and Technology, 1970
- Stepwise Release of Fission Gas from UO2 FuelNuclear Applications, 1966