Fission gas release from power-ramped UO2 fuel
- 30 June 1986
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 139 (2) , 106-112
- https://doi.org/10.1016/0022-3115(86)90028-0
Abstract
No abstract availableThis publication has 9 references indexed in Scilit:
- Comment on the diffusion of fission gas in UO2 during power transients at high burn-upJournal of Nuclear Materials, 1985
- The International DEMO-RAMP-II Project at StudsvikNuclear Technology, 1985
- Local fission gas release and swelling in water reactor fuel during slow power transientsJournal of Nuclear Materials, 1985
- Transiente spaltgasfreisetzung und UO2-mikrostruktur bei leistungsrampenJournal of Nuclear Materials, 1984
- Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel under Normal and Severe Core Accident ConditionsNuclear Technology, 1983
- In-Reactor Measurement of Cladding Strain: Fuel Density and Relocation EffectsNuclear Technology, 1982
- A microstructure-dependent model for fission product gas release and swelling in UO2 fuelNuclear Engineering and Design, 1980
- ELESIM: A Computer Code for Predicting the Performance of Nuclear Fuel ElementsNuclear Technology, 1979
- The effect of grain size on the swelling and gas release properties of uo2 during irradiationJournal of Nuclear Materials, 1974