Fission gas release and swelling in uranium–plutonium mixed nitride fuels
- 1 May 2004
- journal article
- Published by Elsevier BV in Journal of Nuclear Materials
- Vol. 327 (2-3), 77-87
- https://doi.org/10.1016/j.jnucmat.2004.01.002
Abstract
No abstract availableKeywords
This publication has 9 references indexed in Scilit:
- International Conference on East Reactors and Related Fuel Cycles (FR ′91)Journal of Nuclear Science and Technology, 1991
- Fabrication of (U, Pu)N fuel pelletsJournal of Nuclear Materials, 1989
- Dense fuels in EuropeJournal of Nuclear Materials, 1989
- An equation which describes fission gas release from UN reactor fuelJournal of Nuclear Materials, 1988
- Evaluation of the fission gas release behavior from fast reactor mixed oxide fuel based on local concentration measurement of retained xenonJournal of Nuclear Materials, 1988
- Basic aspects of swelling in dense livuid metal fast breeder reactor fuelsJournal of the Less Common Metals, 1986
- Determination of xenon concentrations in nuclear fuels by electron microprobe analysisJournal of Physics D: Applied Physics, 1980
- Fission Gas Release and Microscopic Swelling in Highly Rated Advanced FuelsNuclear Technology, 1980
- Cladding Ovalities in Advanced Liquid-Metal Fast Breeder Reactor Fuel ElementsNuclear Technology, 1976