Development of a fuel element on the basis of the composition (Zr,U)N for a high-temperature reactor

In order to create (Zr,U)N nitride fuel for the first time by direct nitridation of the Zr - 5; 10 % wt. U alloy at 2400°C, using the approach of the oxidative constructing, reproducing the shape of the original metal billet ceramics was obtained. In the process of high-temperature nitridation of th...

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Bibliographic Details
Published in:Journal of physics. Conference series 2018-11, Vol.1134 (1), p.12075
Main Authors: Kovalev, I. A., Shokodko, A.V., Shevtsov, S.V., Ogarkov, A.I., Ashmarin, A.A., Tenishev, A.V., Kolomiets, T.Yu, Shokodko, E.A., Chesnokov, A.A., Shornikov, D.P., Kochanov, G.P., Chernyavskii, A.S., Solntsev, K.A.
Format: Article
Language:English
Subjects:
Fuels
High temperature
Nitrides
Nitrogen
Nuclear fuel elements
Nuclear fuels
Recrystallization
Surface layers
Uranium
Zirconium
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Summary:In order to create (Zr,U)N nitride fuel for the first time by direct nitridation of the Zr - 5; 10 % wt. U alloy at 2400°C, using the approach of the oxidative constructing, reproducing the shape of the original metal billet ceramics was obtained. In the process of high-temperature nitridation of the alloy, a decrease in the uranium content in the near-surface layer occurs with its simultaneous concentration in the unreacted metal phase, in which the formation of three-dimensional defects (cavity) is possible. After the process of complete nitridation of the alloy is completed and it is heated at a synthesis temperature in a nitrogen atmosphere, the collective recrystallization of zirconium nitride occurs, as well as leveling of the concentration of uranium nitride from the volume of the sample to its surface proceeds.
ISSN:1742-6588
1742-6596
DOI:10.1088/1742-6596/1134/1/012075