Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: Uranium diboride and uranium carbide

The challenges and opportunities to alloyed and composite fuel architectures designed and intended to mitigate oxidation of the fuel during a cladding breach of a water-cooled reactor are discussed in this manuscript focused on the oxidation performance of uranium diboride and uranium monocarbide. S...

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Bibliographic Details
Published in:Journal of nuclear materials 2022-03, Vol.560 (-), p.153502, Article 153502
Main Authors: Watkins, Jennifer K., Wagner, Adrian R., Gonzales, Adrian, Jaques, Brian J., Sooby, Elizabeth S.
Format: Article
Language:English
Subjects:
Accident tolerant fuel
accident tolerant fuels
Additives
Alloying
Corrosion
Density
Fuels
high uranium density fuel
NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Nuclear fuels
Nuclear reactors
Oxidation
oxidation corrosion
Reactors
Uranium
Uranium carbide
Uranium diboride
Uranium silicide
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Summary:The challenges and opportunities to alloyed and composite fuel architectures designed and intended to mitigate oxidation of the fuel during a cladding breach of a water-cooled reactor are discussed in this manuscript focused on the oxidation performance of uranium diboride and uranium monocarbide. Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including UN, U3Si2, UB2, and UC. Presented here is the literature for UB2 and UC degradation modes, thermodynamics, and oxidation performance of the pure compounds and reported alloyed and composite architectures. Furthermore, this review covers the materials and techniques for the incorporation of additives, dopants, or composite fuel architectures to improve the oxidation behavior for high uranium density fuels for use in LWRs.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2021.153502