Fission-product release during postirradiation annealing of several types of coated fuel particles
- 31 August 1984
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 125 (3) , 304-319
- https://doi.org/10.1016/0022-3115(84)90558-0
Abstract
No abstract availableKeywords
This publication has 10 references indexed in Scilit:
- Raman Spectral Characterization of Silicon Carbide Nuclear Fuel CoatingsJournal of the American Ceramic Society, 1983
- Performance of coated UO2 particles gettered with ZrCJournal of Nuclear Materials, 1983
- Irradiation performance of experimental fuel particles coated with silicon-alloyed pyrocarbon: A reviewJournal of Nuclear Materials, 1983
- Fission product behavior in UCxOy fissile particles made from weak-acid resinsJournal of Nuclear Materials, 1981
- Properties of Silicon Carbide for Nuclear Fuel Particle CoatingsNuclear Technology, 1977
- Silver Release from Coated Particle FuelNuclear Technology, 1977
- Stoichiometric Effects on Performance of High-Temperature Gas-Cooled Reactor Fuels from the U-C-O SystemNuclear Technology, 1977
- Metal fission product behaviour in high temperature reactors -UO2 coated particle fuelJournal of Nuclear Materials, 1976
- Influence of Irradiation Temperature, Burnup, and Fuel Composition on Gas Pressure (Xe, Kr, CO, CO2) in Coated Particle FuelsJournal of the American Ceramic Society, 1976
- Annealing Behavior of Neutron-Irradiated Silicon Carbide Temperature MonitorsNuclear Technology, 1972