Nuclear Fuel Based on Uranium-Zirconium Carbonitride

The results of Investigations of the nitrogen and uranium pressure in the system U–Zr–C–N in the temperature range 1873–2073 K and the constructed section of the U–Zr–C–N phase diagram at 1873 K are presented. The behavior of the solid fission products in carbonitride fuel, the interaction of the fu...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2017-12, Vol.123 (2), p.96-104
Main Authors: Chernikov, A. S., Zaitsev, V. A., Khromov, Yu. F.
Format: Article
Language:English
Subjects:
Carbides
CARBONITRIDES
Coatings
Energy industry
FISSION PRODUCTS
FUEL ELEMENTS
GENERAL STUDIES OF NUCLEAR REACTORS
Hadrons
Heavy Ions
High temperature
MATERIALS SCIENCE
MECHANICAL PROPERTIES
NITROGEN
Nuclear Chemistry
Nuclear Energy
Nuclear fuel elements
NUCLEAR FUELS
Nuclear industry
Nuclear Physics
Nuclear power plants
PHASE DIAGRAMS
Physics
Physics and Astronomy
PYROLYTIC CARBON
SILICON
Silicon carbide
Temperature effects
TEMPERATURE GRADIENTS
TEMPERATURE RANGE 1000-4000 K
URANIUM
ZIRCONIUM
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Summary:The results of Investigations of the nitrogen and uranium pressure in the system U–Zr–C–N in the temperature range 1873–2073 K and the constructed section of the U–Zr–C–N phase diagram at 1873 K are presented. The behavior of the solid fission products in carbonitride fuel, the interaction of the fuel with a pyrolytic carbon coating, and the behavior of micro fuel elements based on such fuel during high temperature firing and in the presence of a temperature gradient are examined. The conditions for the preparation of fuel compositions of the type uranium carbonitride in a carbide-silicon matrix and some of its physicochemical and mechanical properties are determined. It is noted that there is promise in using fuel compositions and micro fuel elements based on uranium-zirconium carbonitride for high-temperature applications.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-017-0308-y