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 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 |
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 |
Linear stability analysis of flashing instability based on the homogeneous equilibrium model T Zhang, CS Brooks Nuclear Engineering and Design 373, 110994, 2021 | 7* | 2021 |
Identification of flow regimes in boiling flow with clustering algorithms: An interpretable machine-learning perspective L Zhu, Z Jhia Ooi, T Zhang, CS Brooks, L Pan Applied Thermal Engineering 228, 120493, 2023 | 5 | 2023 |
Validation of SAS4A/SASSYS-1 for predicting steady-state single-phase natural circulation T Zhang, ER Smith, CS Brooks, TH Fanning Nuclear Engineering and Design 377, 111149, 2021 | 5 | 2021 |
Two-dimensional quantitative study of boiling flow evolution in vertical inner-heated annulus channel L Zhu, T Zhang, JL Bottini, CS Brooks International Journal of Heat and Mass Transfer 183, 122190, 2022 | 4 | 2022 |
Stability tests and analysis of a low-pressure natural circulation loop with flashing instability T Zhang, CS Brooks Nuclear Technology 209 (10), 1414-1441, 2023 | 2 | 2023 |
Experimental investigation of two-phase instability in natural circulation with direct transient local measurement T Zhang University of Illinois at Urbana-Champaign, 2019 | 2 | 2019 |
Validation of two-group interfacial area transport equation in boiling flow JL Bottini, T Zhang, CS Brooks International Journal of Heat and Mass Transfer 226, 125515, 2024 | | 2024 |
System code validation in periodic two-phase flow from low-pressure oscillations T Zhang, CS Brooks Applied Thermal Engineering 247, 123089, 2024 | | 2024 |
Modeling the Prismatic HTGR Core in SAM by Representative Channels T Zhang, T Hua, ZJ Ooi, CS Brooks 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2023 | | 2023 |
Simulation of Oscillatory Flow Induced by Flashing Instability Using the ASYST System Analysis Code T Zhang, CS Brooks 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2023 | | 2023 |
Phenomena, mechanism, and prediction of flashing instability investigated by experiments, analytical modeling, and numerical simulation T Zhang University of Illinois at Urbana-Champaign, 2023 | | 2023 |
Representative-cell-based Modeling of HTTF in SAM T Zhang, T Hua, ZJ Ooi, L Zou Argonne National Laboratory (ANL), Argonne, IL (United States), 2022 | | 2022 |
Flow regime identification for boiling flow and study of feed-in information in unsupervised machine learning L Zhu, ZJ Ooi, T Zhang, CS Brooks, LM Pan The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022 | | 2022 |
Validation of interfacial mass transfer closures in drift flux model for condensation flow L Zhu, T Zhang, ZJ Ooi, CS Brooks, J Shan, LM Pan The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022 | | 2022 |
Stability tests and analysis on a low-pressure natural circulation loop with flashing instability T Zhang, CS Brooks The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2022 | | 2022 |
Transient local thermal hydraulics data for two-phase flow instability in natural circulation T Zhang, ZJ Ooi, CS Brooks 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019 | | 2019 |
A new dataset with local measurement and visualization of subcooled boiling in an internally heated annulus channel JL Bottini, L Zhu, ZJ Ooi, T Zhang, CS Brooks 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2019 | | 2019 |