| MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis C Lee, WS Yang Nuclear Science and Engineering 187 (3), 268-290, 2017 | 209 | 2017 |
| Advanced burner test reactor preconceptual design report. YI Chang, PJ Finck, C Grandy, J Cahalan, L Deitrich, F Dunn, D Fallin, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2008 | 196 | 2008 |
| Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios. EA Hoffman, WS Yang, RN Hill Argonne National Lab.(ANL), Argonne, IL (United States), 2008 | 133 | 2008 |
| Long-lived fission product transmutation studies WS Yang, Y Kim, RN Hill, TA Taiwo, HS Khalil Nuclear Science and Engineering 146 (3), 291-318, 2004 | 112 | 2004 |
| Methods and issues for the combined use of integral experiments and covariance data: results of a NEA international collaborative study M Salvatores, G Palmiotti, G Aliberti, P Archier, C De Saint Jean, E Dupont, ... Nuclear Data Sheets 118, 38-71, 2014 | 108 | 2014 |
| Fast reactor physics and computational methods WS Yang Nuclear Engineering and Technology 44 (2), 177-198, 2012 | 107 | 2012 |
| Core design studies for a 1000 MWth advanced burner reactor TK Kim, WS Yang, C Grandy, RN Hill Annals of Nuclear Energy 36 (3), 331-336, 2009 | 86 | 2009 |
| The concept of proliferation-resistant, environment-friendly, accident-tolerant, continual and economical reactor (PEACER) IS Hwang, SH Jeong, BG Park, WS Yang, KY Suh, CH Kim Progress in Nuclear Energy 37 (1-4), 217-222, 2000 | 73 | 2000 |
| High-fidelity light water reactor analysis with the numerical nuclear reactor DP Weber, T Sofu, WS Yang, TJ Downar, JW Thomas, Z Zhong, JY Cho, ... Nuclear Science and Engineering 155 (3), 395-408, 2007 | 69 | 2007 |
| A LMR core thermal-hydraulics code based on the ENERGY Model WS Yang Nuclear Engineering and Technology 29 (5), 406-416, 1997 | 62 | 1997 |
| Blanket design studies of a lead-bismuth eutectic-cooled accelerator transmutation of waste system WS Yang, HS Khalil Nuclear Technology 135 (2), 162-182, 2001 | 52 | 2001 |
| Status report on the Small Secure Transportable Autonomous Reactor (SSTAR)/Lead-cooled Fast Reactor (LFR) and supporting research and development. JJ Sienicki, A Moisseytsev, WS Yang, DC Wade, A Nikiforova, P Hanania, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2008 | 50 | 2008 |
| VARI3D & PERSENT: perturbation and sensitivity analysis MA Smith, C Adams, WS Yang, EE Lewis Argonne National Lab.(ANL), Argonne, IL (United States), 2020 | 49 | 2020 |
| A global approach to the physics validation of simulation codes for future nuclear systems G Palmiotti, M Salvatores, G Aliberti, H Hiruta, R McKnight, P Oblozinsky, ... Annals of Nuclear Energy 36 (3), 355-361, 2009 | 47 | 2009 |
| Methods and issues for the combined use of integral experiments and covariance data M Salvatores, G Palmiotti, G Aliberti, R McKnight, P Archier, ... | 44 | 2013 |
| On the performance of point kinetics for the analysis of accelerator-driven systems M Eriksson, JE Cahalan, WS Yang Nuclear science and engineering 149 (3), 298-311, 2005 | 43 | 2005 |
| A variational nodal approach to 2D/1D pin resolved neutron transport for pressurized water reactors T Zhang, EE Lewis, MA Smith, WS Yang, H Wu Nuclear Science and Engineering 186 (2), 120-133, 2017 | 42 | 2017 |
| Transient capability for a MOC-based whole core transport code DeCART JY Cho, KS Kim, CC Lee, HG Joo, WS Yang, TA Taiwo, J Thomas Transactions of the American Nuclear Society 92, 721-722, 2005 | 40 | 2005 |
| Reconstruction of pin power and burnup characteristics from nodal calculations in hexagonal-Z geometry WS Yang, PJ Finck, H Khalil Nuclear science and engineering 111 (1), 21-33, 1992 | 38 | 1992 |
| A three-dimensional variational nodal method for pin-resolved neutron transport analysis of pressurized water reactors T Zhang, Y Wang, EE Lewis, MA Smith, WS Yang, H Wu Nuclear Science and Engineering 188 (2), 160-174, 2017 | 37 | 2017 |
