2016.10 - 2019.10，法國原子能委員會，博士
2016.10 - 2019.09，法國艾克斯馬賽大學(xué)，能源、輻射與等離子體專業(yè)，博士
2010.09 - 2016.06，法國核能工程師（Titre d'Ingénieur Dipl?mé CTI）
2014.09 - 2016.06，中山大學(xué)，中法核工程與技術(shù)學(xué)院，碩士
2010.09 - 2014.06，中山大學(xué)，中法核工程與技術(shù)學(xué)院，學(xué)士

2025.07 -   至   今 ，上海交通大學(xué)，核科學(xué)與工程學(xué)院，長聘副教授

2022.12 - 2025.07，上海交通大學(xué)，核科學(xué)與工程學(xué)院，長聘教軌副教授
2020.02 - 2022.12，上海交通大學(xué)，核科學(xué)與工程學(xué)院，助理教授

小型核反應(yīng)堆物理分析方法與固有安全技術(shù)：

    > 基于連續(xù)能量蒙特卡羅的高適應(yīng)度群常數(shù)計(jì)算方法

    > 高效堆芯計(jì)算及多物理耦合分析方法

    > 長壽期小型核反應(yīng)堆固有安全反應(yīng)性控制技術(shù)

課題組常年招收博士和碩士，歡迎有志于反應(yīng)堆物理與安全的同學(xué)發(fā)送簡歷到 hui.guo@sjtu.edu.cn

2025-2028 國家自然科學(xué)基金面上項(xiàng)目，全錒系金屬燃料快堆強(qiáng)非均勻堆芯反應(yīng)性反饋計(jì)算與調(diào)控方法研究，主持

2022-2024 國家自然科學(xué)基金青年基金，基于局部慢化能譜的長壽期小型快堆可燃毒物補(bǔ)償控制特性研究，主持

2021-2023 上海市啟明星項(xiàng)目揚(yáng)帆專項(xiàng)，兆瓦級熱管冷卻反應(yīng)堆堆芯基礎(chǔ)研究，主持

2024-2027 核電安全技術(shù)與裝備全國重點(diǎn)實(shí)驗(yàn)室基金，基于人工智能優(yōu)化設(shè)計(jì)的不調(diào)硼壓水堆功率展平方法研究，主持

2024-2026 中核集團(tuán)領(lǐng)創(chuàng)科研項(xiàng)目，小型快中子反應(yīng)堆的高適應(yīng)度蒙卡生成均勻化截面技術(shù)，主持

2022-2024 核反應(yīng)堆系統(tǒng)設(shè)計(jì)技術(shù)重點(diǎn)實(shí)驗(yàn)室基金，顆粒燃料堆芯蒙卡多群截面產(chǎn)生及局部非均勻計(jì)算方法研究，主持

一作及通訊作者論文：

[1] Guo H, Wu Y, Song Q, Shen Y, Gu H*. Development of multi-group Monte-Carlo transport and depletion coupling calculation method and verification with metal-fueled fast reactor[J]. Nuclear Science and Techniques, 2023, 34(11): 163.

[2] Guo H, Huo X, Feng K, Gu H*. Verification of OpenMC for fast reactor physics analysis with China Experimental Fast Reactor start-up tests[J]. Nuclear Engineering and Technology, 2022, 54(10): 3897–3908.

[3] Guo H, Wu Y, Song Q, Cong T, Gu H*. Development of OpenMC/Trivac two-step scheme for fast reactor core neutronics analysis[J]. Annals of Nuclear Energy, 2023, 190: 109861.

[4] Guo H, Han S, Jin X, Wu Y, Song Q, Xiao Y, Gu H*. Pareto front of sodium void worth and breeding ratio in metal-fueled sodium fast reactor with axially heterogeneous core design by coupling neutronics and genetic algorithm[J]. Nuclear Engineering and Design, 2024, 429: 113598.

[5] Guo H*, Buiron L, Sciora P, Kooyman T. Designs of control rods with strong absorption ability for small fast reactors[J]. Nuclear Engineering and Design, 2020, 368: 110799.

[6] Guo H, Jin X, Huo X, Gu H*, Wu H. Influence of nuclear data library on neutronics benchmark of China Experimental Fast Reactor start-up tests[J]. Nuclear Engineering and Technology, 2022, 54(10): 3888–3896.

[7] Guo H, Peng X, Wu Y, Jin X, Feng K, Gu H*. Neutronics modelling of control rod compensation operation in small modular fast reactor using OpenMC[J]. Nuclear Engineering and Technology, 2022, 54(3): 803–810.

[8] Guo H, Feng K, Wu Y, Jin X, Huo X, Gu H*. Preliminary verification of multi-group cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark[J]. Progress in Nuclear Energy, 2022, 154: 104484.

[9] Guo H, Feng K, Gu H*, Xiao Y, Liu B. Neutronics modelling of megawatt-class heat pipe reactors[J]. Annals of Nuclear Energy, 2021, 154: 108140.

[10] Guo H*, Buiron L, Sciora P, Kooyman T. Optimization of reactivity control in a small modular sodium-cooled fast reactor[J]. Nuclear Engineering and Technology, 2020, 52(7): 1367–1379.

[11] Guo H*, Archier P, Vidal J-F, Buiron L. Advanced method for depletion calculation of control rods in sodium fast reactors[J]. Annals of Nuclear Energy, 2019, 129: 160–168.

[12] Guo H#,*, Garcia E#,*, Faure B#,*, Buiron L, Archier P, Sciora P, Rimpault G. Advanced method for neutronic simulation of control rods in sodium fast reactors: Numerical and experimental validation[J]. Annals of Nuclear Energy, 2019, 129: 90–100.

[13] Guo H*, Buiron L, Kooyman T, Sciora P. Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators[J]. Annals of Nuclear Energy, 2019, 132: 713–722.

[14] Guo H*, Sciora P, Kooyman T, Buiron L, Rimpault G. Application of boron carbide as burnable poison in sodium fast reactors[J]. Nuclear Technology, 2019, 205(11): 1433–1446.

[15] Guo H*, Kooyman T, Sciora P, Buiron L. Application of minor actinides as burnable poisons in sodium fast reactors[J]. Nuclear Technology, 2019, 205(11): 1447–1459.

[16] Guo H*, Sciora P, Buiron L, Kooyman T. Design directions of optimized reactivity control systems in sodium fast reactors[J]. Nuclear Engineering and Design, 2019, 341: 239–247.

[17] Wu Y, Shen Y, Jin X, Song Q, Xiao Y, Guo H*, Gu H. Development of a design method for burnable poisons in small modular fast reactors[J]. Annals of Nuclear Energy, 2025, 211: 111008.

[18] Feng K, Song Q, Shen Y, Lou L, Xiao Y, Guo H*, Gu H. Development and verification of an MC/MOC two-step scheme for neutronic analysis of FCM-fueled micro gas-cooled reactor[J]. Annals of Nuclear Energy, 2025, 211: 110940.

[19] Song Q, Wang R, Guo H*, Gu H*. MC/MOC two-step method for reactor physics analysis of helical cruciform fuel reactor[J]. Progress in Nuclear Energy, 2025, 180: 105607.

[20] Jin X, Sun Y, Guo H*, Chen L, Jiang X, Wang L, Gu H. Core design and reactivity control optimization of small lead-cooled reactor LFR-180[J]. Nuclear Engineering and Design, 2024, 419: 112950.

[21] Song Q, Zhang C, Wu Y, Feng K, Guo H*, Gu H*. Time-dependent neutron transport method based on three-dimensional method of characteristics[J]. Annals of Nuclear Energy, 2024, 199: 110334.

[22] Song Q, Zhang C, Wu Y, Feng K, Guo H*, Gu H. Multi-objective optimization of method of characteristics parameters based on genetic algorithm[J]. Annals of Nuclear Energy, 2023, 194: 110096.

[23] Song Q-F, Zhu L, Guo H*, Su J*. Verification of neutron-induced fission product yields evaluated by a tensor decomposition model in transport-burnup simulations[J]. Nuclear Science and Techniques, 2023, 34(2): 32.

[24] Wu Y, Song Q, Feng K, Vidal J-F, Gu H, Guo H*. Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis[J]. Nuclear Engineering and Technology, 2023, 55(7): 2474–2482.

[25] Wu Y, Song Q, Wang R, Xiao Y, Gu H, Guo H*. Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis[J]. Nuclear Engineering and Technology, 2023, 55(6): 2112–2124.

[26] Jin X, Zhang Z, Sun Y, Liu M, Xiao Y, Guo H*, Jiang X, Chen L, Gu H. Preliminary safety comparison of lead-cooled fast reactors with advanced fuels in unprotected transients[J]. Nuclear Engineering and Design, 2023, 411: 112419.

[27] Zhang C, Song Q, Guo H*, Cong T, Xiao Y, Gu H*. Reactivity control optimization of boron-free small modular pressurized water reactor with helical-cruciform metallic fuel[J]. Nuclear Engineering and Design, 2023, 414: 112593.

[28] Feng K, Wu Y, Hu J, Jin X, Gu H, Guo H*. Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor[J]. Nuclear Engineering and Design, 2021, 388: 111622.

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