| In-and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR Y Jin, W Xu, X Liu, X Cheng Annals of Nuclear Energy 80, 322-337, 2015 | 52 | 2015 |
| Investigation of the thermal-hydraulic non-equilibrium in a 7× 7 rod bundle during reflood Y Jin, FB Cheung, SM Bajorek, K Tien, CL Hoxie International Journal of Heat and Mass Transfer 127, 266-279, 2018 | 29 | 2018 |
| Experimental study of droplet sizes across a spacer grid location under various reflood conditions Y Jin, FR Beck, BR Lowery, DJ Miller, FB Cheung, SM Bajorek, K Tien, ... Experimental Thermal and Fluid Science 94, 246-257, 2018 | 26 | 2018 |
| Uncertainty analysis on droplet size measurement in dispersed flow film boiling regime during reflood using image processing technique Y Jin, DJ Miller, S Qiao, A Rau, S Kim, FB Cheung, SM Bajorek, K Tien, ... Nuclear Engineering and Design 326, 202-219, 2018 | 26 | 2018 |
| Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF Y. Jin, F.B. Cheung, K. Shirvan, S.M. Bajorek, K. Tien,C.L. Hoxie Annals of Nuclear Energy 148, 2020 | 19 | 2020 |
| Study of the film boiling heat transfer and two-phase flow interface behavior using image processing Y Jin, K Shirvan International Journal of Heat and Mass Transfer 177, 121517, 2021 | 18 | 2021 |
| Progress in reflood thermal hydraulics studies in the past 40 years BW Yang, SM Bajorek, Y Jin, FB Cheung Nuclear Engineering and Design 376, 111073, 2021 | 18 | 2021 |
| Development of a droplet breakup model for dry spacer grid in the dispersed flow film boiling regime during reflood transients Y. Jin, F.B. Cheung, K. Shirvan, S.M. Bajorek, K. Tien,C.L. Hoxie International Journal of Heat and Mass Transfer 143, 2019 | 16 | 2019 |
| Development of a two-phase flow mass quality correlation in the post-dryout DFFB regime during reflood transients Yue Jin, Fan-Bill Cheung, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie International Journal of Heat and Mass Transfer 137, 1076-1087, 2019 | 12 | 2019 |
| System code evaluation of near-term accident tolerant claddings during pressurized water reactor station blackout accidents Y Jin, X Wu, K Shirvan Nuclear Engineering and Design 368, 110814, 2020 | 11 | 2020 |
| EFFECTS OF SYSTEM PARAMETERS ON THE TWO-PHASE FLOW AND HEAT TRANSFER BEHAVIOR IN A ROD BUNDLE Grant R. Garrett, Faith R. Beck, Yue Jin, Fan Bill Cheung, Stephen M ... Proceedings of the 4th Thermal and Fluid Engineering Conference, TFEC2019 …, 2019 | 10* | 2019 |
| Assessment of coated cladding impact on large-break LOCA with TRACE-DAKOTA Y Jin, K Shirvan Nuclear Engineering and Design 374, 111036, 2021 | 8 | 2021 |
| Development of a new spacer grid pressure drop model in rod bundle for the post-dryout two-phase flow regime during reflood transients Y Jin, FB Cheung, K Shirvan, SM Bajorek, K Tien, CL Hoxie Nuclear Engineering and Design 368, 110815, 2020 | 7 | 2020 |
| INVESTIGATION OF TWO-PHASE FLOW THERMAL-HYDRAULIC BEHAVIOR IN ROD BUNDLE DURING REFLOOD TRANSIENTS BASED ON THE RBHT EXPERIMENTAL DATA Y Jin Penn State University (Source: https://etda.libraries.psu.edu/catalog …, 2019 | 7 | 2019 |
| Investigation of two-phase pressure drop across a spacer grid in the dispersed flow film boiling regime Y Jin, L Mohanta, FR Beck, DJ Miller, FB Cheung, SM Bajorek, K Tien, ... 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2017 | 5 | 2017 |
| Effects of period and flow rate on liquid entrainment and the droplet field under forced oscillatory reflood conditions FR Beck, Y Jin, L Mohanta, S Qiao, A Rau, DJ Miller, FB Cheung, ... 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2017 | 5 | 2017 |
| Validation and Uncertainty Quantification of Transient Reflood Models Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT Benchmark Y. Jin, S.M. Bajorek, F.B. Cheung Nuclear Science and Engineering, 2022 | 4* | 2022 |
| Constructing A New CHF Look-Up Table Based on the Domain Knowledge Informed Machine Learning Methodology Y. Jin, X.G. Zhao, K. Shirvan 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022 | 4* | 2022 |
| A Study of Liquid Entrainment in Oscillatory Flows F. R. Beck, Y. Jin, F.B. Cheung, S. M. Bajorek, K. Tien and C. L. Hoxie Embedded Topical International Topical Meeting on Advances in Thermal …, 2018 | 4* | 2018 |
| Investigation of the Two-Phase Flow Interface Behavior during Quench based on Advanced Imaging Processing Y Jin, A Seshadri, K Shirvan Transactions of the American Nuclear Society 123 (2020), 2020 | 3 | 2020 |
Koroush ShirvanProfessor of Nuclear Engineering, MITVerified email at mit.edu
