Follow
Travis W. Knight
Travis W. Knight
Professor and Chair, Department of Mechanical and Nuclear Engineering
Verified email at sc.edu - Homepage
Title
Cited by
Cited by
Year
Laboratory production of zirconium carbide compacts for use in inert matrix fuels
G Vasudevamurthy, TW Knight, E Roberts, TM Adams
Journal of Nuclear Materials 374 (1-2), 241-247, 2008
802008
Model of U3Si2 fuel system using BISON fuel code
KE Metzger, TW Knight, RL Williamson
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2014
752014
Design and fabrication of an advanced TRISO fuel with ZrC coating
IE Porter, TW Knight, MC Dulude, E Roberts, J Hobbs
Nuclear Engineering and Design 259, 180-186, 2013
492013
Determination of mechanical behavior of U3Si2 nuclear fuel by microindentation method
KE Metzger, TW Knight, E Roberts, X Huang
Progress in Nuclear Energy 99, 147-154, 2017
332017
Evaluation of multiple, self-recycling of reprocessed uranium in LWR
JR Coleman, TW Knight
Nuclear engineering and design 240 (5), 1028-1032, 2010
282010
Effect of system parameters on size distribution of 304 stainless steel particles produced by electrical discharge mechanism
G Vasudevamurthy, TW Knight
Materials Letters 61 (27), 4872-4874, 2007
282007
Lattice Parameter Behavior with Different Nd and O Concentrations in (U1−yNdy)O2±X Solid Solution
SM Lee, TW Knight, SL Voit, RI Barabash
Nuclear Technology 193 (2), 287-296, 2016
222016
Enhanced thermal conductivity for LWR fuel
JA Khan, TW Knight, SB Pakala, W Jiang, R Fang, JS Tulenko
Nuclear technology 169 (1), 61-72, 2010
222010
Benchmark of advanced burner test reactor model using MCNPX 2.6. 0 and ERANOS 2.1
K Allen, T Knight, S Bays
Progress in Nuclear Energy 53 (6), 633-644, 2011
212011
Processing and fabrication of mixed uranium/refractory metal carbide fuels with liquid-phase sintering
TW Knight, S Anghaie
Journal of nuclear materials 306 (1), 54-60, 2002
212002
Virtual radiation fields—a virtual environment tool for radiological analysis and simulation
TW Knight, GR Dalton, JS Tulenko
Nuclear Technology 117 (2), 255-266, 1997
191997
Production of high-density uranium carbide compacts for use in composite nuclear fuels
G Vasudevamurthy, TW Knight
Nuclear technology 163 (2), 321-327, 2008
182008
Destruction rate analysis of transuranic targets in sodium-cooled fast reactor (SFR) assemblies using MCNPX and SCALE 6.0
K Allen, T Knight
Progress in Nuclear Energy 52 (4), 387-394, 2010
172010
Measurement of the oxygen partial pressure and thermodynamic modeling of the U–Nd–O system
SM Lee, TW Knight, JW McMurray, TM Besmann
Journal of Nuclear Materials 473, 272-282, 2016
162016
Multimegawatt NEP with vapor core reactor MHD
B Smith, T Knight, S Anghaie
AIP Conference Proceedings 608 (1), 609-616, 2002
152002
Fuel cycle analysis of GFR using advanced fuels
TQ Foley, TW Knight
Progress in Nuclear Energy 51 (1), 109-123, 2009
132009
UPDATED U3SI2 thermal creep model and sensitivity analysis of the U3SI2-SIC accident tolerant FUEL
JA Yingling, KA Gamble, E Roberts, RA Freeman, TW Knight
Journal of Nuclear Materials 543, 152586, 2021
122021
Estimation of specific mass for multimegawatt NEP systems based on vapor core reactors with MHD power conversion
T Knight, S Anghaie
AIP Conference Proceedings 699 (1), 379-387, 2004
112004
Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor
S Patnaik, DA Lopes, TM Besmann, BW Spencer, TW Knight
Review of Scientific Instruments 91 (3), 2020
102020
Cation and vacancy disorder in U1− yNdyO2. 00− x alloys
RI Barabash, SL Voit, DS Aidhy, SM Lee, TW Knight, DJ Sprouster, ...
Journal of Materials Research 30 (20), 3026-3040, 2015
102015
The system can't perform the operation now. Try again later.
Articles 1–20