| 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 |
| Prognostics and health management in nuclear power plants: an updated method-centric review with special focus on data-driven methods X Zhao, J Kim, K Warns, X Wang, P Ramuhalli, S Cetiner, HG Kang, ... Frontiers in Energy Research 9, 696785, 2021 | 50 | 2021 |
| CTF Validation and Verification RK Salko Jr, AJ Wysocki, A Toptan, N Porter, X Zhao, TS Blyth, ... Oak Ridge National Laboratory, 2020 | 42* | 2020 |
| System Risk Quantification and Decision Making Support using Functional Modeling and Dynamic Bayesian Network J Kim, X Zhao, AUA Shah, HG Kang Reliability Engineering & System Safety 215, 107880, 2021 | 22 | 2021 |
| 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 |
| Assessment of the subchannel code CTF for single- and two-phase flows X Zhao, AJ Wysocki, K Shirvan, RK Salko Nuclear Technology 205 (1-2), 338–351, 2019 | 15 | 2019 |
| A weighted multi-output neural network model for the prediction of rigid pavement deterioration F Guo, X Zhao, J Gregory, R Kirchain International Journal of Pavement Engineering 23 (8), 2631-2643, 2022 | 13 | 2022 |
| Machine learning-based critical heat flux predictors in subcooled and low-quality flow boiling X Zhao, RK Salko, K Shirvan International Topical Meeting on Advances in Thermal Hydraulics (ATH 2018) 2 …, 2018 | 12 | 2018 |
| CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors R Salko, A Wysocki, T Blyth, A Toptan, J Hu, V Kumar, C Dances, W Dawn, ... Nuclear Engineering and Design 397, 111927, 2022 | 11 | 2022 |
| Validation and benchmarking of CTF for single- and two-phase flow using VIPRE-01 X Zhao, K Shirvan, RK Salko, AJ Wysocki 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2017 | 11 | 2017 |
| Summary of CTF accuracy and fidelity improvements in FY17 RK Salko, MOG Delchini, X Zhao, WD Pointer, WL Gurecky DOE Consortium for Advanced Simulation of Light Water Reactors, 2017 | 10 | 2017 |
| Bayesian network–based fault diagnostic system for nuclear power plant assets X Zhao, X Wang, MW Golay Nuclear Technology 209 (3), 401-418, 2023 | 9 | 2023 |
| The pursuit of net-positive sustainability for industrial decarbonization with hybrid energy systems X Zhao, AJ Huning, J Burek, F Guo, DJ Kropaczek, WD Pointer Journal of Cleaner Production 362, 132349, 2022 | 9 | 2022 |
| Prediction of Steam-Water Flow Boiling Critical Heat Flux in Tubes and Annuli Using Physics-Informed Deep Feed-Forward Neural Networks X Zhao Massachusetts Institute of Technology, 2018 | 8 | 2018 |
| Mechanistic modeling of departure from nucleate boiling under transient scenarios X Zhao, AJ Wysocki, RK Salko, K Shirvan International Congress on Advances in Nuclear Power Plants (ICAPP 2018) 1 …, 2018 | 8 | 2018 |
| State-of-Technology and Technical Challenges in Advanced Sensors, Instrumentation, and Communication to Support Digital Twin for Nuclear Energy Application V Yadav, V Agarwal, P Jain, P Ramuhalli, X Zhao, C Ulmer, J Carlson, ... U.S. Nuclear Regulatory Commission, 2023 | 5 | 2023 |
| Technical Challenges and Gaps in Integration of Advanced Sensors, Instrumentation, and Communication Technologies with Digital Twins for Nuclear Application V Yadav, V Agarwal, P Jain, P Ramuhalli, X Zhao, C Ulmer, J Carlson, ... 13th International Topical Meeting on Nuclear Plant Instrumentation, Control …, 2023 | 4 | 2023 |
| Constructing a New CHF Look-Up Table Based on the Domain Knowledge Informed Machine Learning Methodology Y Jin, X Zhao, K Shirvan 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022 | 4 | 2022 |
| Hybrid Improved Empirical Mode Decomposition and Artificial Neural Network Model for the Prediction of Critical Heat Flux (CHF) M Djeddou, X Zhao, IA Hameed, A Rahmani 28th International Conference on Nuclear Engineering (ICONE28), 2021 | 4 | 2021 |
| Symptom-Based Conditional Failure Probability Estimation for Selected Structures, Systems, and Components X Zhao, M Golay Massachusetts Institute of Technology, 2020 | 4 | 2020 |
Robert SalkoResearch Scientist, Oak Ridge National LaboratoryVerified email at ornl.gov
