2016.10 - 2019.10，法国原子能和替代能源委员会，Cadarache中心，博士
2016.10 - 2019.09，法国艾克斯马赛大学，能源、辐射与等离子体专业，博士
2010.09 - 2016.06，法国核能工程师（Titre d'Ingénieur Diplômé CTI）
2014.09 - 2016.06，中山大学，中法核工程与技术学院，硕士
2010.09 - 2014.06，中山大学，中法核工程与技术学院，学士

2023.02 - 至今， 我校，核科学与我学院，副教授
2020.02 - 2023.01，我校，核科学与我学院，助理教授

2021年 - 至今，我校致远荣誉计划博士生班主任

反应堆物理分析方法与固有安全共性技术：
方向1：全谱系小堆物理分析方法
方向2：长寿期反应性控制技术
方向3：瞬时负反馈强化技术
课题组常年招收博士和硕士，欢迎有志于反应堆物理与安全的同学发送简历到 hui.guo@sjtu.edu.cn

主持项目：
2022-2024 国家自然科学基金青年项目，基于局部慢化能谱的长寿期小型快堆可燃毒物补偿控制特性研究，主持
2022-2024 核反应堆系统设计技术重点实验室运行基金，颗粒燃料堆芯蒙卡多群截面产生及局部非均匀计算方法研究，主持
2021-2023 上海市扬帆计划，兆瓦级热管冷却反应堆堆芯基础研究，主持
2022-2023 国防科研项目，铅铋快堆堆芯***，主持
2022-2023 国防科研项目，长寿命高燃耗***，主持
主参项目：
2022-2025 国家自然科学基金重点项目，十字螺旋金属燃料多物理耦合分析方法及其特性研究，主参
2022-2024 国电投-交大未来能源计划联合基金项目，先进固态热管堆关键分析软件研发及试验研究，主参

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.

工程学导论，大一下，48学时
核反应堆物理分析，大三上，48学时
科学研究与创新实践，大三下，16学时
本科生毕业设计，8人次
本科生创新实践（PRP），8人次
本科生全员导师，6人次

1. 一种高精度复杂能谱微堆多群截面制作方法，发明专利
2. 测量高温高压水介质下管系流致声共振的热态试验系统，发明专利
3. 种测量棒束通道内格架下游的壁面压力场的实验装置，发明专利
4. 超临界二氧化碳冷却反应堆安全限值计算与瞬态安全分析软件，软著
5. 铅基堆精细化子通道瞬态分析软件，软著
6. 螺旋燃料堆芯精细化瞬态安全分析软件，软著

中国核学会会员
Nuclear Engineering and Design，Annals of Nuclear Energy， Nuclear Technology，International Journal of Energy Research等期刊审稿人

2019，中国国家优秀自费留学生奖
2021，上海市*****人才计划