Background

Advanced nuclear fuels and materials, spent fuel handling and disposition, transportable and micro-reactor design, space nuclear power and propulsion, nuclear safeguards, and the integration of nuclear energy into non-electric applications such as clean fuel production and industrial decarbonization.

Education

• Ph.D., Nuclear Engineering Science, University of Florida, 2000
• M.S., Nuclear Engineering Science, University of Florida, 1995
• B.S., Nuclear Engineering, University of Florida, 1994

Awards

• Fellow of the American Nuclear Society, 2024
• Breakthrough Leadership in Research Award, University of South Carolina, 2020
• Research Achievement Award, College of Engineering, University of South Carolina, 2018
• 2012 Joseph M. Biedenbach Distinguished Service Award, University of South Carolina
• 2011 Fred C. Davison Distinguished Scientist Award
• Significant Contribution Award by Material Science and Technology Division of the American Nuclear Society, 2001
• National engineering honor society Tau Beta Pi
• Nuclear-engineering honor society Alpha Nu Sigma

Selected Publications

• Aaron Horwood, Juan Vitali, Andrew Thueme, Ruddie Ibanez, Travis Knight, “DOD’s Need for a Transportable Energy Solution: The Promise of Nuclear Power” Joint Force Quarterly 113 (2nd Quarter 2024).
• Robert J. Demuth, Robert Sindelar, Anna d’Entremont, Rebecca Smith, and Travis W. Knight, “Post-Drying Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels”, Nuclear Technology, April 2024.
• Sudipta Saha, Jamil Khan, Travis Knight, Tanvir Farouk, “A Global Model for Predicting Vacuum Drying of Used Nuclear Fuel Assemblies”, Nuclear Technology, 2021.
• J. A Yingling, K.A Gamble, Elwyn Roberts, R. Austin Freeman, and Travis W. Knight, Updated U3Si2 Thermal Creep Model and Sensitivity Analysis Of The U3Si2-Sic Accident Tolerant Fuel, Journal of Nuclear Materials, January 2021.
• Metzger, Kathryn E.; T. W. Knight, E. Roberts, X. Huang; “Determination of Mechanical Behavior of U3Si2 Nuclear Fuel by Microindentation Method”, Progress in Nuclear Energy, 99, 2017, pages 147-154.
• Lee, SeungMin, T. W. Knight, J. W. McMurray, and T. M. Besmann, Measurement of the oxygen partial pressure and thermodynamic modeling of the U–Nd–O system, Journal of Nuclear Materials, 473, May 2016, pages 272-282.
• Meredith, A. D., T. W. Knight, R. Noe, "Modified Sodium Diuranate Process for the Recovery of Uranium from Uranium Hexafluoride Transport Cylinder Wash Solution", Separation Science and Technology, Volume 50, Issue 6, 2015, pp 920-925.
• Inabinett, D., T. W. Knight, J. Gray, and T. Adams, “Study of XeF2 fluorination potential against Rh2O3, RuO2, ZrO2, and U3O8 for use in reactive gas recycle of used nuclear fuel”, Progress in Nuclear Energy, 76, September 2014, Pages 106–111.
• Porter, I. E., T. W. Knight, M.C. Dulude, E. Roberts, and J. Hobbs, “Design and fabrication of an advanced TRISO fuel with ZrC coating”, Nuclear Engineering and Design, 259, June 2013, pp.180–186.
• Read, Jr., C. M., T. W. Knight, K. S. Allen, “Development of a Multi-Tiered Recycling Strategy with a Sodium-Cooled Heterogeneous Innovative Burner Reactor,” Progress in Nuclear Energy, 62, January 2013, pp. 72-78.
• Allen, K.S.; T. W. Knight, C. M. Read Jr., “Design of an Equilibrium Core 1000 MWt Sodium-Cooled Heterogeneous Innovative Burner Reactor,” Nuclear Engineering and Design, 242, January 2012, pp. 108–114.
• Vasudevamurthy, G., T. W. Knight, T. M. Adams**, and E. Roberts, “Production and Characterization of ZrC-UC Inert Matrix Composite Fuel for Gas Fast Reactors”, Nuclear Technology, 173, 2, February 2011, pp. 200-209.
• Coleman, J. R. and T. W. Knight, “Evaluation of multiple, self-recycling of reprocessed uranium in LWR”, Nuclear Engineering and Design, 240 (2010), pp. 1028-1032.
• Vasudevamurthy, G., T. W. Knight, “Production of High Density Uranium Carbide compacts for use in Composite Nuclear Fuels”, Nuclear Technology, 163, 2, August 2008, pp. 321-327.
• Knight, T. W. and S. Anghaie, “Processing and Fabrication of Mixed Uranium/Refractory Metal Carbide Fuels with Liquid-Phase Sintering” Journal of Nuclear Materials, 306, November 2002, pp. 54-60.
• Knight, T. W., G. R. Dalton, and J. S. Tulenko, "Virtual Radiation Fields--A Virtual Environment Tool for Radiological Analysis and Simulation," Nuclear Technology, 117, 2, February 1997, pp. 255-266.