Robert K. Salko, Ph.D.
Affiliations: | 2012 | Pennsylvania State University, State College, PA, United States |
Area:
Nuclear EngineeringGoogle:
"Robert Salko"Parents
Sign in to add mentor| Maria Avramova | grad student | 2012 | Penn State | |
| (Improvement of COBRA-TF for modeling of PWR cold- and hot-legs during reactor transients.) | ||||
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Publications
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| Zhao X, Shirvan K, Salko RK, et al. (2020) On the prediction of critical heat flux using a physics-informed machine learning-aided framework Applied Thermal Engineering. 164: 114540 |
| Salko RK, Pointer WD, Delchini M, et al. (2019) Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF Nuclear Technology. 205: 1697-1706 |
| Toptan A, Salko RK, Avramova MN, et al. (2019) A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation Nuclear Engineering and Design. 341: 248-258 |
| Zhao X, Wysocki AJ, Shirvan K, et al. (2018) Assessment of the Subchannel Code CTF for Single- and Two-Phase Flows Nuclear Technology. 205: 338-351 |
| Toptan A, Porter NW, Salko RK, et al. (2018) Implementation and assessment of wall friction models for LWR core analysis Annals of Nuclear Energy. 115: 565-572 |
| Kochunas B, Collins B, Stimpson S, et al. (2017) VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion Nuclear Science and Engineering. 185: 217-231 |
| Aviles BN, Kelly DJ, Aumiller DL, et al. (2017) MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6 Progress in Nuclear Energy. 101: 338-351 |
| Kelly DJ, Kelly AE, Aviles BN, et al. (2017) MC21/CTF and VERA multiphysics solutions to VERA core physics benchmark progression problems 6 and 7 Nuclear Engineering and Technology. 49: 1326-1338 |
| Salko RK, Schmidt RC, Avramova MN. (2015) Optimization and parallelization of the thermal-hydraulic subchannel code CTF for high-fidelity multi-physics applications Annals of Nuclear Energy. 84: 122-130 |
| Sung Y, Kucukboyaci VN, Cao L, et al. (2015) COBRA-TF evaluation and application For PWR steamline break DNB analysis International Topical Meeting On Nuclear Reactor Thermal Hydraulics 2015, Nureth 2015. 1: 324-337 |