| A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents T Sofu Nuclear engineering and technology 47 (3), 227-239, 2015 | 98 | 2015 |
| 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 |
| Hydrodynamic forces on inundated bridge decks K Kerenyi, T Sofu, J Guo | 64 | 2009 |
| Investigation of aerodynamic influence on truck platooning P Vegendla, T Sofu, R Saha, MM Kumar, LK Hwang SAE Technical Paper, 2015 | 62 | 2015 |
| Regulatory Technology Development Plan Sodium Fast Reactor. Mechanistic Source Term Development DS Grabaskas, AJ Brunett, MD Bucknor, JJ Sienicki, T Sofu Argonne National Lab.(ANL), Argonne, IL (United States), 2015 | 35 | 2015 |
| Sodium fast reactor safety and licensing research plan-volume I M Denman, J LaChance, T Sofu, G Flanagan, R Wigeland, R Bari SAND2012-4260, Sandia National Laboratories, Albuquerque, New Mexico, 2012 | 32 | 2012 |
| Modeling and simulation functional needs for molten salt reactor licensing BR Betzler, F Heidet, B Feng, C Rabiti, T Sofu, NR Brown Nuclear Engineering and Design 355, 110308, 2019 | 29 | 2019 |
| EBR-II passive safety demonstration tests benchmark analyses-phase 2 L Briggs, W Hu, GH Su, B Vezzoni, A Del Nevo, S Monti, D Sui, L Maas, ... 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2015 | 28 | 2015 |
| Experimental observations on electrorefining spent nuclear fuel in molten LiCl-KCl/liquid cadmium system SX Li, T Sofu, TA Johnson, DV Laug Journal of New Materials for Electrochemical Systems 3 (3), 259-268, 2000 | 27 | 2000 |
| Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety R Schmidt, T Sofu, T Wei, J Thomas, R Wigeland, J Carbajo, H Ludewig, ... SAND2011-4145. June, 2011 | 25 | 2011 |
| The long-life core encapsulated nuclear heat source (ENHS) generation IV reactor E Greenspan, A Barak, D Saphier, J Buongiorno, NW Brown, Q Hossain, ... American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL …, 2002 | 24 | 2002 |
| ENHS: The encapsulated nuclear heat source—A nuclear energy concept for emerging worldwide energy markets DC Wade, E Feldman, J Sienicki, T Sofu, A Barak, E Greenspan, ... International Conference on Nuclear Engineering 35960, 583-590, 2002 | 24 | 2002 |
| Development of phenomena identification and ranking table for Westinghouse lead fast reactor's safety J Liao, P Ferroni, RF Wright, U Bachrach, JH Scobel, T Sofu, AM Tentner, ... Progress in Nuclear Energy 131, 103577, 2021 | 20 | 2021 |
| FIPD: The SFR metallic fuels irradiation & physics database AM Yacout, K Mo, A Oaks, Y Miao, T Sofu, W Mohamed Nuclear Engineering and Design 380, 111225, 2021 | 18 | 2021 |
| Requirements for advanced simulation of nuclear reactor and chemicalseparation plants G Palmiotti, J Cahalan, P Pfeiffer, T Sofu, T Taiwo, T Wei, M Willamson Argonne National Laboratory, 2006 | 14 | 2006 |
| Coupled calculations using the numerical nuclear reactor for integrated simulation of neutronic and thermal-hydraulic phenomena DP Weber, T Sofu, WS Yang, T DOWNAR, J THOMAS, Z Zhong, HG Joo Proc. Physics of Fuel Cycles and Advanced Nuclear Systems: Global …, 2004 | 14 | 2004 |
| Benchmark analyses of sodium natural convection in the upper plenum of the MONJU reactor vessel H Ohira, Y Xu, U Bieder, K Velusamy, H Mochizuki, S Choi, Y Shvetsov, ... Int. Conf. Fast Reactors and Related Fuel Cycles: Safe Technologies and …, 2013 | 13 | 2013 |
| Applicability of commercial CFD tools for assessment of heavy vehicle aerodynamic characteristics D Pointer, T Sofu, J Chang, D Weber The Aerodynamics of Heavy Vehicles II: Trucks, Buses, and Trains, 349-361, 2009 | 13 | 2009 |
| The numerical nuclear reactor-a high fidelity, integrated neutronic, thermal-hydraulic and thermo-mechanical code DP Weber, T Sofu, P Pfeiffer, WS Yang, KS Kim, TH Chun, T Downar, ... | 13 | 2005 |
| The Numerical Nuclear Reactor for High Fidelity Integrated Simulation of Neutronic, Thermal-Hydraulic and Thermo Mechanical Phenomena—Project Overview DP Weber, T Sofu, PA Pfeiffer, WS Yang, TA Taiwo, HG Joo, JY Cho, ... Proc. Physics of Fuel Cycles and Advanced Nuclear Systems: Global …, 2004 | 13 | 2004 |
