Faculty

Associate Professor

zhanghuang@tsinghua.edu.cn

010-89796058

Education

Ph.D., Tsinghua University, Nuclear Science and Technology, 2015

M.S., Tsinghua University, Computer Science and Technology, 2019

B.S., Sichuan University, Nuclear Engineering and Technology, 2010


Work Experience

06/2022 – now, Associate Professor, Division of Thermal Hydraulics, INET, Tsinghua University

04/2021 – 05/2022, Assistant Professor, Division of Thermal Hydraulics, INET, Tsinghua University

10/2017 02/2021, Research Scientist, Department of Energy, Environmental and Chemical Engineering, Washington University in St. Louis, U.S.

09/2015 – 09/2017, Postdoctoral Researcher, Department of Thermal Engineering, Tsinghua University


Social service

Teaching

Introduction to Nuclear Reactor Engineering


Journal Reviewer

Nuclear Engineering and Design, Annuals of Nuclear Energy, Nuclear Engineering and Technology, Progress in Nuclear Energy, International Journal of Hydrogen Energy, Chemical Engineering and Science, etc.

Service to Professional Associations

Member, Nuclear Heat for Non-Electric & Cogeneration Application Working Group, Generation IV International Forum, 2024-now

Technical Secretary, Research Reactor & New Reactor Development Branch, Chinse Nuclear Society, 2024-now

Broad Director, Chinese Society of Particuology, 2022-now


Areas of Research Interests/ Research Projects

Complex Multiphase Flow in Advanced Nuclear Reactor, including theory and experimental techniques of complex multiphase flow, theory and applications of nuclear hydrogen production, artificial intelligence in advanced nuclear reactor design

Research Status

1. National Natural Science Foundation of China (NSFC), "Study on the flow and heat transfer mechanism in a novel catalytic bed unit of steam reformer for hydrogen production using High Temperature Gas-Cooled Reactor (HTGR)", USD 75,000, 2024-2027, No. 12375170. (PI)

2. China National Nuclear Corporation (CNNC) Elite Talent Program, "Research on thermal-hydraulics and process enhancement for hydrogen production of steam-reforming using High Temperature Gas-Cooled Reactor (HTGR)", USD 230,000, 2023-2026. (PI)

3. Beijing Municipal Natural Science Foundation, "Study on design theory and fabrication method of hydrogen permeable membrane reactor for hydrogen production using nuclear energy", USD 28,500, No. 1242020, 2023-2026. (Co-PI)

4. Beijing Municipal Natural Science Foundation, "Research on Viral Droplet Airborne Propagation Laws and Barrier Methods", USD 28,500, No. 3212017, 2021-2023. (PI)

5. Beijing Nature Fund Youth Project, "Study on the Dynamic Behavior and Mechanism of Collision Process of Fine Particle-Wet Wall Impact System", USD 14,285, No. 3184051, 2019-2020. (PI)


Honors and Awards

Several students in my group were awarded, including Best Thesis Performance of Tsinghua University, First (or Second) Class Scholarship of Tsinghua University, IAEA Scholarship, etc.

Selected Academic Achievement

[1] Wu, C., Wu, B., Zhang, H.* and Yin, H., 2025. Study on the performance of membrane reactor using steam methane reforming for hydrogen production heated by HTGR. Nuclear Engineering and Technology, p.103744.

[2] Peng, L., Zhang, S., Zhang, H., Zhao, J., Jiang, K., Zheng, W., Du, B., Yin, H., He, X. and Ma, T., 2025. Study on permeability from 3D images of nuclear grade graphite IG-110 by the multidimensional capillary bundle model, lattice Boltzmann method and experiment. Annals of Nuclear Energy, 213, p.111144.

[3] Wu, C.Y., Zhang, H.*, Wang, Z.Y., Yin, H., 2025. Comprehensive study on parameter sensitivity analysis of steam reformer tube for hydrogen production using HTGR. Annals of Nuclear Energy, 213, 111159.

[4] Peng, L., Zhang, S., Zhang, H., et al., 2025. Study on permeability from 3D images of nuclear grade graphite IG-110 by the multidimensional capillary bundle model, lattice Boltzmann method and experiment. Annals of Nuclear Energy, 213, 111144.

[5] Zheng, W., Li, H., Du, B., Zhang, H., Yin, H., He, X. and Ma, T., 2024. Corrosion behaviors of Inconel 617 and Incoloy 800H in impure helium with different CO contents at high temperatures. Progress in Nuclear Energy, 172, p.105188.

[6] Liu, R., Li, H., Zhang, H.*, Yin, H., Ma, T., 2024. Study on tritium permeation behavior in primary and second circuits of the hydrogen production system by methane steam reforming using HTGR. Nuclear Engineering and Design, 421, p.113101.

[7] Du, B., Zhang, H., Zheng, W., Li, H., He, X., Ma, T., Yin, H., 2024. Carburization and tensile behavior of Alloy 617 in impure helium containing a part-per-million level of CH4 at 950 ◦C. Corrosion Science, 227, p.111660.

[8] Zheng, W., Zhang, H., Du, B., Li, H., Yin, H., He, X. and Ma, T., 2023. Effect of impurity ratios on the high-temperature corrosion of Inconel 617 and Incoloy 800H in impure helium. Annals of Nuclear Energy, 189, p.109836.

[9] Li, H., Zhang, H., Zheng, W., Du, B., Yin, H., He, X., Ma, T. and Yang, X., 2023. Study on oxidation kinetics of three kinds of candidate superalloys for VHTR under air ingress accident. Annals of Nuclear Energy, 189, p.109844.

[10] Zhang, Y., Zhang, H., Liu, Q., Zhou, J., 2023. Application of one-dimensional heat and mass transfer model of helium heated reformer coupled with HTR-10, Annals of Nuclear Energy, 189, p.109769.

[11] Liu, Q., Ma, Y. and Zhang, H.*, 2023. Numerical investigation on droplet collision phenomena in moisture separators using population balance model under Lagrangian framework. Annals of Nuclear Energy, 186, p.109722.

[12] Zheng, W., Zhang, H., Du, B., Li, H., Yin, H., He, X. and Ma, T., 2022. High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment. Science and Technology of Nuclear Installations, 2022.

[13] Zhang, Y., Zhang, H., Liu, Q., Zhou, J. 2022. Numerical simulation on flow and reaction characteristics for catalytic region in helium-heated steam reformer coupled with HTR-10. Progress in Nuclear Energy, 154, p. 104435.

[14] Ma, Y., Zhang, H. and Liu, Q., 2022. Experimental study on spreading and splashing behavior of continuous droplets impacting on heated wall. International Journal of Heat and Mass Transfer, 196, p. 123219.

[15] Hu, G., Zhang, H., Liu, Q., 2022. Assessment on population balance model and wall boiling model for subcooled boiling flow of steam generator of nuclear power plant. Annals of Nuclear Energy, 173, p. 109128.

[16] Hu, G., Zhang, H. and Liu, Q., 2022. Design optimization on characteristics of packed-bed thermal energy storage system coupled with high temperature gas-cooled reactor pebble-bed module. Energy Conversion and Management, 257, p.115434.

[17] Ma, Y., Hu, G., Zhang, H. and Liu, Q., 2022. Comparison of breakup and coalescence kernels in population balance model for modeling isothermal gas-liquid flow. Nuclear Engineering and Design, 388, p.111616.

[18] Okonkwo, O., Zhang, H., Li, K., Liu, Q. and Biswas, P., 2022. Thermodynamic analysis of hydrocarbon reforming. Journal of CO2 Utilization, 60, p.101998.