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 - Funding Information:
Work at the collaborating institutions, including Westinghouse Electric Company, was supported by the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract 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. All work performed at Idaho National Laboratory was conducted under the prime contract: DE-AC07–05ID14517. This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.
Funding Information:
Work at the collaborating institutions, including Westinghouse Electric Company, was supported by the U.S. Department of Energy , Office of Nuclear Energy under DOE Idaho Operations Office Contract 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 . All work performed at Idaho National Laboratory was conducted under the prime contract: DE-AC07–05ID14517 .
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 - https://www.scopus.com/pages/publications/85122529389
UR - https://www.mendeley.com/catalogue/664e1a3d-5889-3809-93de-6da805007e24/
U2 - 10.1016/j.jnucmat.2021.153502
DO - 10.1016/j.jnucmat.2021.153502
M3 - Review article
AN - SCOPUS:85122529389
SN - 0022-3115
VL - 560
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153502
ER -