TY - JOUR
T1 - Challenges and Opportunities to Alloyed and Composite Fuel Architectures to Mitigate High Uranium Density Fuel Oxidation
T2 - Uranium Mononitride
AU - Watkins, Jennifer K.
AU - Gonzales, Adrian
AU - Wagner, Adrian R.
AU - Sooby, Elizabeth S.
AU - Jaques, Brian J.
N1 - Publisher Copyright:
© 2021
PY - 2021/9
Y1 - 2021/9
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 mononitride. Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including one on each: UN, U3Si2, UC and UB2. Presented here is the research motivation for the incorporation of additives, dopants, or composite fuel architectures to improve the oxidation/corrosion behavior of high uranium density nuclear fuels for use in LWRs. Furthermore, this review covers the literature on the degradation modes, thermodynamics, and oxidation performance of pure UN and UN-compounds as well as reported alloyed and composite architectures.
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 mononitride. Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including one on each: UN, U3Si2, UC and UB2. Presented here is the research motivation for the incorporation of additives, dopants, or composite fuel architectures to improve the oxidation/corrosion behavior of high uranium density nuclear fuels for use in LWRs. Furthermore, this review covers the literature on the degradation modes, thermodynamics, and oxidation performance of pure UN and UN-compounds as well as reported alloyed and composite architectures.
KW - Accident tolerant fuels
KW - Composite fuels
KW - Oxidation
KW - Uranium mononitride
UR - http://www.scopus.com/inward/record.url?scp=85106637317&partnerID=8YFLogxK
UR - https://scholarworks.boisestate.edu/mse_facpubs/480
U2 - 10.1016/j.jnucmat.2021.153048
DO - 10.1016/j.jnucmat.2021.153048
M3 - Review article
SN - 0022-3115
VL - 553
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153048
ER -