| 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 | 86 | 2008 |
| 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 | 83 | 2014 |
| 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 | 54 | 2013 |
| 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 | 39 | 2017 |
| Evaluation of multiple, self-recycling of reprocessed uranium in LWR JR Coleman, TW Knight Nuclear engineering and design 240 (5), 1028-1032, 2010 | 29 | 2010 |
| 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 | 28 | 2007 |
| 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 | 24 | 2016 |
| 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 | 23 | 2010 |
| 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 | 23 | 2002 |
| 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 | 22 | 2011 |
| Production of high-density uranium carbide compacts for use in composite nuclear fuels G Vasudevamurthy, TW Knight Nuclear technology 163 (2), 321-327, 2008 | 20 | 2008 |
| 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 | 19 | 1997 |
| 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 | 18 | 2010 |
| 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 | 16 | 2016 |
| 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 | 15 | 2021 |
| Multimegawatt NEP with vapor core reactor MHD B Smith, T Knight, S Anghaie AIP Conference Proceedings 608 (1), 609-616, 2002 | 15 | 2002 |
| Fuel cycle analysis of GFR using advanced fuels TQ Foley, TW Knight Progress in Nuclear Energy 51 (1), 109-123, 2009 | 13 | 2009 |
| Mechanistic verification of empirical UO2 fuel fracture models KA Gamble, TW Knight, E Roberts, JD Hales, BW Spencer Journal of Nuclear Materials 556, 153163, 2021 | 12 | 2021 |
| Separate-Effects Tests for Studying Temperature-Gradient-Driven Cracking in UO2 Pellets S Patnaik, BW Spencer, E Roberts, TM Besmann, TW Knight Nuclear Science and Engineering 195 (12), 1307-1326, 2021 | 11 | 2021 |
| 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 | 11 | 2020 |
Jamil KhanProfessor of Mechanical Engineering, University of South Carolina確認したメール アドレス: sc.edu