TY - JOUR
T1 - Challenges and Opportunities to Alloyed and Composite Fuel Architectures to Mitigate High Uranium Density Fuel Oxidation: Uranium Silicide
AU - Gonzales, Adrian
AU - Watkins, Jennifer K.
AU - Wagner, Adrian R.
AU - Jaques, Brian J.
AU - Sooby, Elizabeth S.
N1 - Gonzales, Adrian; Watkins, Jennifer K.; Wagner, Adrian R.; Jaques, Brian J.; and Sooby, Elizabeth S. (2021). "Challenges and Opportunities to Alloyed and Composite Fuel Architectures to Mitigate High Uranium Density Fuel Oxidation: Uranium Silicide". Journal of Nuclear Materials, 553, 153026. https://doi.org/10.1016/j.jnucmat.2021.153026
PY - 2021/9/1
Y1 - 2021/9/1
N2 - The challenges and opportunities to alloyed and composite fuel architectures designed and intended to mitigate oxidation of the fuel during a cladding breech of a water-cooled reactor are discussed in three review manuscripts developed in parallel, with the presented article focused on the oxidation performance of uranium silicide. Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including UN, U 3 Si 2 , UC and UB 2 . Presented here are the literature for the U 3 Si 2 degradation modes, thermodynamics, and oxidation performance of the pure compound and its 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/corrosion 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 breech of a water-cooled reactor are discussed in three review manuscripts developed in parallel, with the presented article focused on the oxidation performance of uranium silicide. Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including UN, U 3 Si 2 , UC and UB 2 . Presented here are the literature for the U 3 Si 2 degradation modes, thermodynamics, and oxidation performance of the pure compound and its 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/corrosion behavior for high uranium density fuels for use in LWRs.
UR - https://scholarworks.boisestate.edu/mse_facpubs/479
UR - https://doi.org/10.1016/j.jnucmat.2021.153026
M3 - Article
JO - Materials Science and Engineering Faculty Publications and Presentations
JF - Materials Science and Engineering Faculty Publications and Presentations
ER -