● 2004 - 2008 　Xi’an Jiaotong University, Xi’an, China 　Ph.D. 　Engineering Thermophysics

● 2001 - 2004　 Xi’an Jiaotong University, Xi’an China　 M.S. 　Thermal Engineering

● 1997 - 2001　 Xi’an Jiaotong University, Xi’an China　 B.S. 　Thermal Engineering

● 2023- 　Tsinghua University, Beijing, China　 Tenured Associate Professor

● 2016 - 2023　Tsinghua University, Beijing, China　Tenure-track Associate Professor

● 2010-2016　 Tsinghua University, Beijing, China　Research Assistant Professor

● 2011-2012 　Pohang University of Science and Technology, Pohang, Korea　Postdoctoral

● 2008-2010 　Shanghai Jiaotong University, Shanghai, China　Postdoctoral

A list of the courses he delivered is as follows:

● NPP Systems and Equipment for undergraduate students (Fall semester, average 30 students)

● Nuclear Reactor Safety Analysis for undergraduate students (Fall semester, average 30 students)

● Nuclear Engineering Virtual Simulation Experiments for undergraduate students (Spring &Fall semester, average 40 students)

● Nuclear Reactor Engineering for graduate students (Fall semester, average 10 students)

● Advanced Thermal Analysis of Nuclear Reactors for graduate students (Spring semester, about 30 students)

63 master's and 7 doctoral students have successfully completed their degree programs under Dr. Huang’s guidance. Currently, he is supervising 16 PhD students and 14 MS students.

His research interests are in numerical simulation and high-performance computation, thermohydraulic and safety analysis of nuclear reactors, and addressing the immediate requirements of special purpose nuclear reactors.

In the area of numerical simulation, his focus is on development of novel methods to expand functionality and improve computing efficiency. His latest work is to explore further possibilities in the field of neutronic-thermohydraulic/multi-physics coupling calculation based on RMC code (a computational Monte Carlo code for nuclear reactors, developed by REAL research team, Department of Engineering Physics, THU).

As to thermohydraulic and safety analysis, he has focused on the research of steady and transient hi-fidelity analysis methods for HPRs (Heat Pipe-cooled Reactors), which laid a solid foundation for related engineering software, thus promoting the development of HPRs. His CFD work is related to MD, LBM, VOF, and system code.

In 2014, he started establishing the Nuclear Engineering Virtual Simulation Laboratory (NEVSL) to cater the teaching requirements. The Phase I of the project was completed in 2020. Since then, the laboratory has obtained significant supports from the educational and industrial sectors. The laboratory has created multiple simulation platforms covering typical reactors such as PWR, SFR, HTGR, and HPR, for both normal operation and severe accident scenarios.

The laboratory is currently in the third phase of development, aimed at creating a comprehensive virtual simulation network platform based on AI technology for nuclear engineering. This platform will integrate experiment teaching, student competitions, and scientific research to meet the urgent needs of people at different levels, both within and outside the campus.

He has published more than peer-reviewed 100 papers in international journals with more than 1200 citations, and an H-factor = 23 (as of August 2025). 1 article was selected as a cover article in the Journal of Nuclear Material. Three papers were shortlisted as CNKI Highly Cited Papers.

Part of the publishing journals include Journal of Fluid Mechanics, Computer Physics Communications, Journal of Computational Physics, Journal of Nuclear Material, Nuclear Science and Engineering, Annals of Nuclear Energy, Progress of Nuclear Energy, Nuclear Engineering Design, International Journal of Heat and Mass Transfer.

Some publications are listed as follows since 2023:

[1] Xingyu Zhao, Guodong Liu, Shanfang Huang, Kan Wang, Qiaoyan Chen, Guoming Liu, Neutronic and thermal-hydraulics coupling analyses on prismatic TRISO-fueled gas-cooled reactors using Monte Carlo and Computational Fluid Dynamics method, Computer Physics Communications. 315(2025):109724.

[2] Qifan Wang, Junren Hou, Shanfang Huang, Fangbei Chen, Minyun Liu, Ruohan Zheng, Yanping Huang, Lie Quan, Houjun Gong, and Yu Tang, Carbon Dioxide Bubble Dynamics and Wall Heat Transfer in Flash Chambers: Nucleation Departure and Cold Bubble Effects, Annals of Nuclear Energy 218 (2025) 111371.

[3] Hao Luo, Kaiwen Li, Jie Li, Zhaoyuan Liu, Jingang Lianga, Jiyang Yu, Shanfang Huang, Kan Wang, Enhancing accuracy and efficiency of RMC/SUBCHAN neutronics and thermal-hydraulics coupling system for BEAVRS simulation, Progress in Nuclear Energy 183 (2025) 105666.

[4] Junren Hou, Minyun Liu,Shanfang Huang(2025)., Boltzmann simulations of Rayleigh-Bénard convection with compressibility-induced non-Oberbeck-Boussinesq effects, Journal of Fluid Mechanics, 1009, A49.

[5] Hao Luo; Kaiwen Li; Nan An; Shanfang Huang; Kan Wang(2025), New RMC Energy Deposition Treatment and its Application inMulti-Physics Simulation, Nuclear Science and Engineering, 199: S966–S986.

[6] Chengyuan Li; Leran Guo; Shanfang Huang; Jian Deng(2025), Optimization and simulation of startup control for space nuclear power systems with closed brayton cycle based on NuHeXSys, Progress in Nuclear Energy 180 (2025) 105610.

[7] Hou, Junren; Zhou, Yuan; Huang, Shanfang, Conjugate heat transfer analysis of helium-xenon gas mixture in tight rod bundles, Applied Thermal Engineering 252 (2024) 123661.

[8]  Minyun Liu; Shenghui Liu; Yanping Huang; Ruohan Zheng; Haohan Yuan; Jie Wa ng; Houjun Gong; Yanlin Wang; Shanfang Huang, Pool heat transfer studies of near-critical and supercritical carbon dioxide International Journal of Heat and Mass Transfer 229 (2024) 125669

[9]  Hao Luo; Shanfang Huang; Kan Wang; Xiang Xiao, A newly developed and verified transport capacity of Monte Carlo photon particles in RMC, Computer Physics Communications 294 (2024) 108935.

[10] Zhichao Qi; Wenbin Han; Minyun Liu; Chengzhi Ji; Hongbin Wei; Shanfang Huang, NTPSS-vPower: A model for system simulation of a nuclear thermal propulsion system, Annals of Nuclear Energy 192 (2023) 110019.

[11] Hao Luo; Shanfang Huang; Kan Wang, Towards optimized designs for control rod absorbers with a high-fidelity simulation method implemented in the RMC code, Annals of Nuclear Energy 191 (2023) 109910.

[12] Mingqiang Song; Shanfang Huang; Chenfeng Mo; Guohan Chai; Zhiyi Yang, Uncertainty and sensitivity analysis of iodine release in severe accidents of advanced pressurized water reactors based on the Latin Hypercube method and Grey Correlation Coefficients, Nuclear Engineering and Design 412 (2023) 112450.

[13] Yugao Ma; Xueqing Wang; Hongxing Yu; Shanfang Huang; Yingnan Zhang; G.H. Su; Jian Deng; Xiaoming Chai; Wenzhen Hu, Capillary limit of a sodium screen-wick heat pipe, Applied Thermal Engineering 232 (2023) 120972.

[14] Yugao Ma; Hongxing Yu; Xueqing Wang; Yingnan Zhang; Shanfang Huang; Chenglong Wang; G.H. Su; Xiaoqiang He; Ruicheng Zhong; Jian Deng, Experimental study on sodium Screen-Wick heat pipe capillary limit, Applied Thermal Engineering 227 (2023) 120397.

● Member of the Board of Directors (since 2022), for Reactor Thermal Fluids Society Branch of Chinese Nuclear Society.

● Deputy Director (since 2020), for Expert Committee on Nuclear Engineering Branch in Virtual Simulation Consortium of China.

● Member of the Board of Directors (since 2019), for Nuclear Energy Kinetics Society Branch of Chinese Nuclear Society.

● Member of the Board of Directors (since 2019), for Beijing Nuclear Society.

● TPC Member (since 2018), for CNNC Software and Digital Reactor Engineering Center.

● TPC Member, ICONE, NURETH, WORTH, and NUTHOS.

● Teaching awards: Dr. Huang’s teaching performance has ranked in the top 5% at the university level for seven times, and he has won the annual teaching excellence award of Tsinghua University for five times. "'Nuclear Reactor System and Equipment' Teaching Case" and "Nuclear Reactor Virtual Simulation Experiment' Teaching Case" won the first and second prize of the Teaching Achievement Award of the China Nuclear Industry Education Society in 2023 and 2025, respectively.
● Academic conference awards: Best paper of International Conference on Nuclear Engineering (ICONE), International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH), China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH), Annual Meeting of the Key Laboratory of Nuclear Reactor System Design and Technology, National Key Laboratory of Advanced Nuclear Energy Technology, and Academic Annual Meeting of the Reactor Thermal and Hydraulic Branch Excellent papers
● Graduate students’ awards: Dozens of students have won the President Scholarship, and the National Scholarship. He has instructed students to obtain excellent graduation design, excellent master's thesis and excellent doctoral dissertation at Tsinghua University, and excellent doctoral dissertation in Beijing.
● Contest awards: Relying on the nuclear engineering virtual simulation laboratory of Tsinghua University, he has won the second prize of the Challenge Cup, the first prize and the second prize of the Beijing Virtual Simulation Competition.