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Taiyang Zhang
Taiyang Zhang
Postdoctoral Research Associate, University of Illinois at Urbana-Champaign
在 illinois.edu 的电子邮件经过验证 - 首页
标题
引用次数
引用次数
年份
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
192020
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
92020
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
82020
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
52023
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
52021
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
42022
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
22023
Experimental investigation of two-phase instability in natural circulation with direct transient local measurement
T Zhang
University of Illinois at Urbana-Champaign, 2019
22019
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
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