| Experimental investigation of variability in bubble departure characteristics between nucleation sites in subcooled boiling flow ZJ Ooi, V Kumar, JL Bottini, CS Brooks International Journal of Heat and Mass Transfer 118, 327-339, 2018 | 28 | 2018 |
| Experimental database of two-phase natural circulation with local measurements ZJ Ooi, V Kumar, CS Brooks Progress in Nuclear Energy 116, 124-136, 2019 | 25 | 2019 |
| Identification of flow regimes in boiling flows in a vertical annulus channel with machine learning techniques ZJ Ooi, L Zhu, JL Bottini, CS Brooks International Journal of Heat and Mass Transfer 185, 122439, 2022 | 21 | 2022 |
| Experimental study of boiling flow in a vertical heated annulus with local two-phase measurements and visualization JL Bottini, L Zhu, ZJ Ooi, T Zhang, CS Brooks International Journal of Heat and Mass Transfer 155, 119712, 2020 | 19 | 2020 |
| Experimental study of wall nucleation characteristics in flow boiling under subatmospheric pressures in a vertical square channel N Colgan, JL Bottini, ZJ Ooi, CS Brooks International Journal of Heat and Mass Transfer 134, 58-68, 2019 | 18 | 2019 |
| Forced convection steam-water experimental database in a vertical annulus with local measurements V Kumar, ZJ Ooi, CS Brooks International Journal of Heat and Mass Transfer 137, 216-228, 2019 | 16 | 2019 |
| Bubble diameter distribution and intergroup mass transfer coefficient in flows with phase change L Zhu, ZJ Ooi, JL Bottini, CS Brooks, J Shan International Journal of Heat and Mass Transfer 163, 120456, 2020 | 9 | 2020 |
| Experimental dataset with high-speed visualization for vertical upward steam-water flow with transition from annulus to circular channel ZJ Ooi, T Zhang, CS Brooks International Journal of Heat and Mass Transfer 161, 120281, 2020 | 9 | 2020 |
| Validation of the interfacial area transport equation coupled with the void transport equation for prediction of flashing flows ZJ Ooi, V Kumar, CS Brooks Nuclear Science and Engineering 194 (8-9), 598-619, 2020 | 8 | 2020 |
| A multi-dimensional dataset for two-phase instability in low pressure natural circulation based on direct transient local measurement T Zhang, ZJ Ooi, M Skrzypek, CS Brooks International Journal of Heat and Mass Transfer 151, 119447, 2020 | 8 | 2020 |
| Two-group interfacial area transport equation coupled with void transport equation in adiabatic steam water flows ZJ Ooi, CS Brooks International Journal of Heat and Mass Transfer 177, 121531, 2021 | 7 | 2021 |
| Ring Model Development and Validation for Prismatic HTGR Core Thermal-hydraulics and Safety Analysis T Hua, ZJ Ooi, R Hu, L Zou Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 6 | 2021 |
| Identification of flow regimes in boiling flow with clustering algorithms: An interpretable machine-learning perspective L Zhu, ZJ Ooi, T Zhang, CS Brooks, L Pan Applied Thermal Engineering 228, 120493, 2023 | 5 | 2023 |
| Modeling sensitivity in prediction of interfacial area concentration in boiling flow L Zhu, ZJ Ooi, CS Brooks, J Shan Progress in Nuclear Energy 133, 103638, 2021 | 5 | 2021 |
| Report on Year-3 of Water NSTF Matrix Testing: Two-Phase Parametric Test Series Q Lv, D Lisowski, M Jasica, R Hu, A Kraus, ZJ Ooi, N Bremer, M Farmer Argonne National Lab.(ANL), Argonne, IL (United States), 2021 | 4 | 2021 |
| FY21 Progress on Computational Modeling of the Water-Based NSTF Q Lv, A Kraus, Z Ooi, R Hu, D Lisowski Argonne National Lab (ANL), Lemont, IL (United States), ANL-ART-235, 2021 | 4 | 2021 |
| Current Intergroup mass transfer limitations in the multi-group two-fluid model L Zhu, ZJ Ooi, CS Brooks 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019 | 4 | 2019 |
| Simulation of the high temperature test facility (httf) core using the 2d ring model with sam ZJ Ooi, T Hua, L Zou, R Hu Nuclear Science and Engineering 197 (5), 840-867, 2023 | 3 | 2023 |
| Modeling of a Generic Pebble Bed High-temperature Gas-cooled Reactor (PB-HTGR) with SAM ZJ Ooi, L Zou, T Hua, J Fang, R Hu Argonne National Lab.(ANL), Argonne, IL (United States), 2022 | 3 | 2022 |
| Effect of inlet throttling on thermohydraulic instability in a large scale water-based RCCS: A system-level analysis with RELAP5-3D ZJ Ooi, Q Lv, R Hu, M Jasica, D Lisowski Nuclear Engineering and Technology 56 (5), 1902-1912, 2024 | 2 | 2024 |
Caleb S. BrooksAssociate Professor, University of Illinois在 illinois.edu 的电子邮件经过验证
