威尼斯娱人城官网

1. 2016.10 – 2019.09: Ph.D. in Nuclear Reactor Physics
*Commissariat à l'énergie atomique et aux énergies alternatives, CEA/DEN/DER/SPRC/LE2C, Cadarache, France
*Ecole Doctorale 352, Physique et Sciences de la Matière, Aix-Marseille Université, France
*Thesis title: Design of innovative systems for the optimized control of reactivity in Generation-IV fast neutron reactors
*Director: Prof. BUIRON Laurent.
2. 2010.09 - 2016.06: Bachelor, Master, and French CTI Engineer in Nuclear Engineering and Science
*Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai, China

2023.02 - Present: Associate Professor
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, China
2020.02 - 2023.02: Assistant Professor
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, China

Nuclear Reactor Physics and Inherent Safety Technologies

1. H. Guo, K. Feng, Y. Wu, X. Jin, X. Huo, H. Gu*, Preliminary verification of multi-group cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark, Progress in Nuclear Energy, 2022.
2. H. Guo, X. Jin, X. Huo, H. Gu*, H. Wu, Influence of nuclear data library on neutronics benchmark of China Experimental Fast Reactor start-up tests, Nuclear Engineering and Technology, 2022.
3. H. Guo, X. Huo, H. Gu*, K. Feng, Verification of OpenMC for fast reactor physics analysis with China Experimental Fast Reactor start-up tests, Nuclear Engineering and Technology, 2022.
4. K. Feng, Y. Wu, J. Hu, X. Jin, H. Gu, H. Guo*, Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor, Nuclear Engineering and Design, 2022.
5. H. Guo, X. Peng, Y. Wu, X. Jin, K. Feng, H. Gu*, Neutronics modelling of control rod compensation operation in small modular fast reactor using OpenMC, Nuclear Engineering and Technology, 2021.
6. H. Guo, K. Y. Feng, H. Y. Gu*, X. Yao, and L. Bo, Neutronic modeling of megawatt-class heat pipe reactors, Annals of Nuclear Energy, 2021.
7. H. Guo*, L. Buiron, P. Sciora, and T. Kooyman, Designs of control rods with strong absorption ability for small fast reactors, Nuclear Engineering and Technology, 2020.
8. H. Guo*, L. Buiron, P. Sciora, and T. Kooyman, Optimization of reactivity control in a small modular sodium-cooled fast reactor, Nuclear Engineering and Technology, 2020.
9. H. Guo*, P. Sciora, L. Buiron, and T. Kooyman, Design Directions of Optimized Reactivity Control Systems in Sodium Fast Reactors, Nuclear Engineering and Technology, 2019.
10. H. Guo*, E. Garcia, B. Faure, L. Buiron, P. Archier, P. Sciora, G. Rimpault, Advanced method for neutronic simulation of control rods in sodium fast reactors: Numerical and Experimental Validation, Annals of Nuclear Energy, 2019.
11. H. Guo*, P. Archier, J. Vidal, L. Buiron, Advanced method for depletion calculation of control rods in sodium fast reactors, Annals of Nuclear Energy, 2019.
12. H. Guo*, P. Sciora, T. Kooyman, L. Buiron, G. Rimpault, Application of boron carbide as burnable poison in sodium fast reactors, Nuclear Technology, 2019.
13. H. Guo*, T. Kooyman, P. Sciora, L. Buiron, Application of Minor Actinides as Burnable Poison in Sodium Fast Reactors, Nuclear Technology, 2019.
14. H. Guo*, L. Buiron, P. Sciora, T. Kooyman, Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators, Annals of Nuclear Energy, 2019.
15. E. Garcia*, P. Sciora, T. Kooyman, G. Rimpault, H. Guo, B. Faure, Flux distribution in the Superphénix start-up core with APOLLO-3, Annals of Nuclear Energy, 2020.
16. T. Cong, Q. Zhang, J. Zhu, Y. Xiao, H. Guo, H. Gu*, Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly, Annals of Nuclear Energy, 2023.
17. L. Liu, D. Zhu, M. Liu, D. Li, H. Guo, Y. Xiao, H. Gu*, Investigation of the safety limits and the limiting safety system settings on a super carbon-dioxide cooled micro modular reactor, Annals of Nuclear Energy, 2023.
18. L. Liu, B. Liu, Y. Xiao, H. Gu*, H. Guo, Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment, Progress in Nuclear Energy, 2022.

Introduction to engineering
Nuclear reactor physics