TY - JOUR
T1 - Challenges and opportunities to alloyed and composite fuel architectures to mitigate high uranium density fuel oxidation: uranium silicide
T2 - uranium silicide
AU - Gonzales, Adrian
AU - Watkins, Jennifer K.
AU - Watkins, Jennifer
AU - Wagner, Adrian R.
AU - Jaques, Brian J.
AU - Sooby, Elizabeth S.
N1 - Funding Information:
This work was supported by the U.S. Department of Energy, Office of Nuclear Energy. This work is also part of a collaboration led by Westinghouse Electric Company comprising several national laboratories, vendors, and universities awarded in response to the DE-NE0008824 funding opportunity. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript or allow others to do so, for U.S. Government purposes. Additional funding for student and faculty support was provided by the U.S. NRC Grant number 31310018M0046 and NNSA MSIPP CONNECT program, Grant Number DE-NA0003948.
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 silicide. Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including UN, U
3Si
2, UC and UB
2. Presented here are the literature for the U
3Si
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
3Si
2, UC and UB
2. Presented here are the literature for the U
3Si
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://doi.org/10.1016/j.jnucmat.2021.153026
UR - http://www.scopus.com/inward/record.url?scp=85105488442&partnerID=8YFLogxK
UR - https://www.mendeley.com/catalogue/7dd42a76-d9b3-31d7-9612-bf3d462db2e1/
U2 - 10.1016/j.jnucmat.2021.153026
DO - 10.1016/j.jnucmat.2021.153026
M3 - Review article
AN - SCOPUS:85105488442
SN - 0022-3115
VL - 553
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153026
ER -