In the Nuclear Safety Analysis Team, I work on the validation and verification of High Temperature Gas-Cooled Reactor (HTGR) performance, safety, digital twin simulators, and techno-economics. I work on well-established proprietary and open-source codes, including but not limited to: RMC, PANGU, NUWA, FIST, FRAT, OpenMC, OpenMOC, OpenFOAM, preCICE. My research works towards:
1. Neutronics, Thermal-Hydraulics, and Mechanics of HTGRs
2. Source Term Analysis of HTGRs
3. Techno-economics of HTGRs
4. HTGR Simulators (Digital Twins)
My training was done in Tsinghua University, where I obtained my Masters and Doctorate in Nuclear Science and Technology (Outstanding Thesis Awards, 1st and 8th in Cohort respectively) from the Institute of Nuclear Energy Science and Engineering Management, Department of Engineering Physics, where the focus of my research was on Stochastic Media Modelling Methods in Monte Carlo codes. I also obtained significant working experience with the National Nuclear Safety Administration of China (NNSA) in terms of simulation code V&V against established benchmarks, as well as with other academic and industrial partners.
Selected Works:
Tan, Z. C., Feng, Z. Y., & Wang, K. (2024). An improved parallel Random Sequential Addition algorithm in RMC code for dispersion fuel analysis. Annals of Nuclear Energy, 201, 110439.
Tan, Z. C., Feng, Z. Y., Chan, K. Y., & Wang, K. (2025). A semi-implicit Chord Length Sampling method for dispersion fuel analysis. Annals of Nuclear Energy, 219, 111436.
Tan, Z. C., Feng, Z. Y., & Wang, K. (2026). An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media. Nuclear Science and Engineering, 200(sup1), S456-S465.
Tan, Z. C., Feng, Z. Y., & Wang, K. (2026). Coupled ODR-DEM methods for dispersion fuel analysis in RMC code. Journal of Nuclear Science and Technology, 63(1), 82-88.
I can be found at https://www.linkedin.com/in/zhe-chuan/ and https://www.researchgate.net/profile/Zhe-Chuan-Tan.
ORCID: 0009-0008-9099-4681