Thermal Energy Transport in Oxide Nuclear Fuel.

Autor: Hurley DH; Idaho National Laboratory, 1955 North Fremont Avenue, Idaho Falls, Idaho 83415, United States., El-Azab A; School of Materials Engineering, Purdue University, 701 West Stadium Avenue, West Lafayette, Indiana 47907, United States., Bryan MS; Materials Science and Technology Division, Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, Tennessee 37831, United States., Cooper MWD; Materials Science and Technology Division, Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545, United States., Dennett CA; Idaho National Laboratory, 1955 North Fremont Avenue, Idaho Falls, Idaho 83415, United States., Gofryk K; Idaho National Laboratory, 1955 North Fremont Avenue, Idaho Falls, Idaho 83415, United States., He L; Idaho National Laboratory, 1955 North Fremont Avenue, Idaho Falls, Idaho 83415, United States., Khafizov M; Department of Mechanical and Aerospace Engineering, The Ohio State University, 201 West 19th Ave, Columbus, Ohio 43210, United States., Lander GH; European Commission, Joint Research Center, Postfach 2340, D-76125 Karlsruhe, Germany., Manley ME; Materials Science and Technology Division, Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, Tennessee 37831, United States., Mann JM; U.S. Air Force Research Laboratory, Sensors Directorate, 2241 Avionics Circle, Wright Patterson AFB, Ohio 45433, United States., Marianetti CA; Department of Applied Physics and Applied Mathematics, Columbia University, 500 West 120th Street, New York, New York 10027, United States., Rickert K; KBR, 2601 Mission Point Boulevard, Suite 300, Dayton, Ohio 45431, United States., Selim FA; Department of Physics and Astronomy, Bowling Green State University, 705 Ridge Street, Bowling Green, Ohio 43403, United States., Tonks MR; Department of Materials Science and Engineering, University of Florida, 158 Rhines Hall, Gainesville, Florida 32611, United States., Wharry JP; School of Materials Engineering, Purdue University, 701 West Stadium Avenue, West Lafayette, Indiana 47907, United States.
Jazyk: angličtina
Zdroj: Chemical reviews [Chem Rev] 2022 Feb 09; Vol. 122 (3), pp. 3711-3762. Date of Electronic Publication: 2021 Dec 17.
DOI: 10.1021/acs.chemrev.1c00262
Abstrakt: To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts seek solid fuels that must withstand unprecedented temperature and radiation extremes. In these advanced fuels, thermal energy transport under irradiation is directly related to reactor performance as well as reactor safety. The science of thermal transport in nuclear fuel is a grand challenge as a result of both computational and experimental complexities. Here we provide a comprehensive review of thermal transport research on two actinide oxides: one currently in use in commercial nuclear reactors, uranium dioxide (UO 2 ), and one advanced fuel candidate material, thorium dioxide (ThO 2 ). In both materials, heat is carried by lattice waves or phonons. Crystalline defects caused by fission events effectively scatter phonons and lead to a degradation in fuel performance over time. Bolstered by new computational and experimental tools, researchers are now developing the foundational work necessary to accurately model and ultimately control thermal transport in advanced nuclear fuels. We begin by reviewing research aimed at understanding thermal transport in perfect single crystals. The absence of defects enables studies that focus on the fundamental aspects of phonon transport. Next, we review research that targets defect generation and evolution. Here the focus is on ion irradiation studies used as surrogates for damage caused by fission products. We end this review with a discussion of modeling and experimental efforts directed at predicting and validating mesoscale thermal transport in the presence of irradiation defects. While efforts in these research areas have been robust, challenging work remains in developing holistic tools to capture and predict thermal energy transport across widely varying environmental conditions.
Databáze: MEDLINE
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