Funder
University of Tennessee
U.S. Department of Energy
Fusion Energy Sciences
Subject
Metals and Alloys,Polymers and Plastics,Ceramics and Composites,Electronic, Optical and Magnetic Materials
Reference77 articles.
1. Properties and characteristics of ZrC;Jackson,2012
2. Fission product release from ZrC-coated fuel particles during postirradiation heating at 1600°C;Minato;J. Nucl. Mater.,1995
3. Retention of fission product caesium in ZrC-coated fuel particles for high-temperature gas-cooled reactors;Minato;J. Nucl. Mater.,2000
4. Properties of zirconium carbide for nuclear fuel applications;Katoh;J. Nucl. Mater.,2013
5. International Atomic Energy Agency IAEA-tecdoc-1645, High Temperature Gas Cooled Reactor Fuels and Materials, Vienna,2010
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