| Multidimensional multiphysics simulation of nuclear fuel behavior RL Williamson, JD Hales, SR Novascone, MR Tonks, DR Gaston, ... Journal of Nuclear Materials 423 (1-3), 149-163, 2012 | 666 | 2012 |
| Finite element analysis of thermal residual stresses at graded ceramicmetal interfaces. Part I. Model description and geometrical effects RL Williamson, BH Rabin, JT Drake Journal of Applied Physics 74 (2), 1310-1320, 1993 | 368 | 1993 |
| BISON theory manual the equations behind nuclear fuel analysis JD Hales, RL Williamson, SR Novascone, G Pastore, BW Spencer, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2016 | 226 | 2016 |
| Finite element analysis of thermal residual stresses at graded ceramicmetal interfaces. Part II. Interface optimization for residual stress reduction JT Drake, RL Williamson, BH Rabin Journal of applied physics 74 (2), 1321-1326, 1993 | 188 | 1993 |
| Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling G Pastore, LP Swiler, JD Hales, SR Novascone, DM Perez, BW Spencer, ... Journal of Nuclear Materials 456, 398-408, 2015 | 172 | 2015 |
| Multidimensional multiphysics simulation of TRISO particle fuel JD Hales, RL Williamson, SR Novascone, DM Perez, BW Spencer, ... Journal of Nuclear Materials 443 (1-3), 531-543, 2013 | 154 | 2013 |
| BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms RL Williamson, JD Hales, SR Novascone, G Pastore, KA Gamble, ... Nuclear Technology 207 (7), 954-980, 2021 | 150 | 2021 |
| Validating the BISON fuel performance code to integral LWR experiments RL Williamson, KA Gamble, DM Perez, SR Novascone, G Pastore, ... Nuclear Engineering and Design 301, 232-244, 2016 | 130 | 2016 |
| Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2±x: Implications for nuclear fuel performance modeling DA Andersson, P Garcia, XY Liu, G Pastore, M Tonks, P Millett, B Dorado, ... Journal of Nuclear Materials 451 (1-3), 225-242, 2014 | 126 | 2014 |
| Three-dimensional simulation of plasma spray: effects of carrier gas flow and particle injection on plasma jet and entrained particle behavior HB Xiong, LL Zheng, S Sampath, RL Williamson, JR Fincke International Journal of Heat and Mass Transfer 47 (24), 5189-5200, 2004 | 122 | 2004 |
| Fabrication of Titanium CarbideAlumina Composites by Combustion Synthesis and Subsequent Dynamic Consolidation BH Rabin, GE Korth, RL Williamson Journal of the American Ceramic Society 73 (7), 2156-2157, 1990 | 111 | 1990 |
| Short-pulse microwave treatment of disseminated sulfide ores JB Salsman, RL Williamson, WK Tolley, DA Rice Minerals Engineering 9 (1), 43-54, 1996 | 107 | 1996 |
| Verification of the BISON fuel performance code JD Hales, SR Novascone, BW Spencer, RL Williamson, G Pastore, ... Annals of Nuclear Energy 71, 81-90, 2014 | 101 | 2014 |
| Development of a multiscale thermal conductivity model for fission gas in UO2 MR Tonks, XY Liu, D Andersson, D Perez, A Chernatynskiy, G Pastore, ... Journal of Nuclear Materials 469, 89-98, 2016 | 100 | 2016 |
| A review of fuel performance modelling P Van Uffelen, J Hales, W Li, G Rossiter, R Williamson Journal of Nuclear Materials 516, 373-412, 2019 | 97 | 2019 |
| Parametric studies of dynamic powder consolidation using a particlelevel numerical model RL Williamson Journal of Applied Physics 68 (3), 1287-1296, 1990 | 90 | 1990 |
| A computational examination of the sources of statistical variance in particle parameters during thermal plasma spraying RL Williamson, JR Fincke, CH Chang Plasma Chemistry and Plasma Processing 20, 299-324, 2000 | 88 | 2000 |
| FEM study of the effects of interlayers and creep in reducing residual stresses and strains in ceramic-metal joints RL Williamson, BH Rabin, GE Byerly Composites Engineering 5 (7), 851-863, 1995 | 85 | 1995 |
| Mechanistic materials modeling for nuclear fuel performance MR Tonks, D Andersson, SR Phillpot, Y Zhang, R Williamson, CR Stanek, ... Annals of nuclear energy 105, 11-24, 2017 | 82 | 2017 |
| Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior RL Williamson Journal of Nuclear Materials 415 (1), 74-83, 2011 | 77 | 2011 |
Stephen NovasconeComputational Scientist, Idaho National Laboratory在 inl.gov 的电子邮件经过验证
