| CTF theory manual R Salko Jr, M Avramova, A Wysocki, A Toptan, J Hu, N Porter, T Blyth, ... (No Title), 2020 | 312* | 2020 |
| VERA core simulator methodology for pressurized water reactor cycle depletion B Kochunas, B Collins, S Stimpson, R Salko, D Jabaay, A Graham, Y Liu, ... Nuclear Science and Engineering 185 (1), 217-231, 2017 | 120 | 2017 |
| On the prediction of critical heat flux using a physics-informed machine learning-aided framework X Zhao, K Shirvan, RK Salko, F Guo Applied Thermal Engineering 164, 114540, 2020 | 100 | 2020 |
| CTF: A thermal hydraulic sub-channel code for LWR transient analyses, user’s manual MN Avramova Pennsylvania State University, Department of Nuclear Engineering, 2009 | 67* | 2009 |
| VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12 A Godfrey, B Collins, KS Kim, J Powers, R Salko, S Stimpson, ... Physics of Reactors 2016: Unifying Theory and Experiments in the 21st …, 2016 | 53 | 2016 |
| Optimization and parallelization of the thermal–hydraulic subchannel code CTF for high-fidelity multi-physics applications RK Salko, RC Schmidt, MN Avramova Annals of Nuclear Energy 84, 122-130, 2015 | 43 | 2015 |
| MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7 DJ Kelly III, AE Kelly, BN Aviles, AT Godfrey, RK Salko, BS Collins Nuclear Engineering and Technology 49 (6), 1326-1338, 2017 | 38 | 2017 |
| CTF validation and verification RK Salko, T Blyth, CA Dances, JW Magedanz, C Jernigan, J Kelly Consortium for Advanced Simulation of Light Water Reactors, CASL-U-2016-1113, 2016 | 34 | 2016 |
| CTF: A thermal hydraulic sub-channel code for LWR transient analyses MN Avramova, RK Salko User’s Manual, Pennsylvania State University, 2009 | 33 | 2009 |
| Coupled neutronics and thermal-hydraulic solution of a full core PWR using VERA-CS S Palmtag, K Clarno, G Davidson, R Salko, T Evans, J Turner, R Schmidt Proceedings of PHYSOR, 2014 | 32 | 2014 |
| Development of COBRA-TF for modeling full-core, reactor operating cycles R Salko, T Lange, V Kucukboyaci, Y Sung, S Palmtag, J Gehin, ... Advances in Nuclear Fuel Management V (ANFM 2015), 2015 | 31 | 2015 |
| COBRA-TF Subchannel Thermal-Hydraulics Code (CTF) Theory Manual RK Salko, MN Avramova Pennsylvania State University, CASL-U-2015-0054-000, State College, 2015 | 29 | 2015 |
| MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem# 6 BN Aviles, DJ Kelly, DL Aumiller, DF Gill, BW Siebert, AT Godfrey, ... Progress in Nuclear Energy 101, 338-351, 2017 | 28 | 2017 |
| DESIGN OF A HIGH FIDELITY CORE SIMULATOR FOR ANALYSIS OF PELLET CLAD INTERACTION. RP Pawlowski Sandia National Lab.(SNL-NM), Albuquerque, NM (United States), 2015 | 24 | 2015 |
| A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation A Toptan, RK Salko, MN Avramova, K Clarno, DJ Kropaczek Nuclear Engineering and Design 341, 248-258, 2019 | 23 | 2019 |
| CTF 4.0 Theory Manual R Salko Jr, M Avramova, A Wysocki, A Toptan, J Hu, N Porter, TS Blyth, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 22 | 2019 |
| Improved departure from nucleate boiling prediction in rod bundles using a physics-informed machine learning-aided framework X Zhao, RK Salko, K Shirvan Nuclear Engineering and Design 374, 111084, 2021 | 20 | 2021 |
| Multiphysics coupling methods for molten salt reactor modeling and simulation in VERA AM Graham, Z Taylor, BS Collins, RK Salko, M Poschmann Nuclear Science and Engineering 195 (10), 1065-1086, 2021 | 19 | 2021 |
| CTF Validation and Verification Manual RK Salko, TS Blyth, CA Dances, JW Magedanz, C Jernigan, J Kelly, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). Consortium for …, 2016 | 18* | 2016 |
| Implementation of two-phase gas transport into VERA for molten salt reactor analysis Z Taylor, R Salko, AM Graham, BS Collins, GI Maldonado Annals of Nuclear Energy 165, 108672, 2022 | 17 | 2022 |
