TY - JOUR
T1 - Challenges and Opportunities to Alloyed and Composite Fuel Architectures to Mitigate High Uranium Density Fuel Oxidation
T2 - Uranium Diboride and Uranium Carbide
AU - Watkins, Jennifer K.
AU - Wagner, Adrian R.
AU - Gonzales, Adrian
AU - Jaques, Brian J.
AU - Sooby, Elizabeth S.
N1 - Publisher Copyright:
© 2021
PY - 2022/3
Y1 - 2022/3
N2 - 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.
AB - 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.
KW - Accident tolerant fuel
KW - Corrosion
KW - Oxidation
KW - Uranium carbide
KW - Uranium diboride
UR - http://www.scopus.com/inward/record.url?scp=85122529389&partnerID=8YFLogxK
UR - https://scholarworks.boisestate.edu/mse_facpubs/506
U2 - 10.1016/j.jnucmat.2021.153502
DO - 10.1016/j.jnucmat.2021.153502
M3 - Review article
SN - 0022-3115
VL - 560
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153502
ER -