Selected Publications
[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] Shen Y, Wu Y, Song Q, Feng K, Guo H*, Gu H. Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo[J]. Annals of Nuclear Energy, 2025, 219: 111448.
[19] Feng K, Song Q, Wang Y, Guo H*, Cong T, Xiao Y, Gu H. Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor[J]. Nuclear Engineering and Technology, 2025, 57(9): 103645.
[20] 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.
[21] 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.
[22] 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.
[23] 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.
[24] 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.
[25] 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.
[26] 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.
[27] 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.
[28] 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.
[29] 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.
[30] 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.