成松柏 - 哈尔滨工程大学 - 核科学与技术学院

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成松柏教授博士生导师收藏完善纠错
哈尔滨工程大学核科学与技术学院
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个人简介

成松柏，男，教授，博士生导师。主要研究方向为液态金属冷却快堆（钠堆、铅堆）等先进核能系统热工水力、安全与严重事故分析。2011年9月博士毕业于日本九州大学核工程系，历任日本九州大学核工程系学术研究员（2011.10～2012.03）、日本原子力研究开发机构（JAEA）液态金属冷却快堆研发中心博士研究员（2012.04～2015.03）、中山大学中法核工程与技术学院副教授（2015.06～2023.09）。围绕液态金属冷却反应堆，以第一/通讯作者已发表近70篇SCI国际期刊论文，以第一发明人已授权4项国家专利，并以第一作者在国防工业出版社、清华大学出版社以及Springer国际出版社共出版著作5部。现担任中国能源学会等学术组织专家委员会委员、国际期刊Frontiers in Energy Research、Frontiers in Nuclear Engineering、Nuclear Science、International Journal of Advanced Nuclear Reactor Design and Technology（JANDT）等编委/青年编委，在Frontiers in Energy Research、Frontiers in Nuclear Engineering、JANDT、Applied Science等国际期刊先后成功举办多个学术专刊，并担任International Symposium on Thermal hYdraulics and Safety of Advanced Nuclear Energy Systems （TYSAN）系列国际学术会议发起人。教育经历 2008.10～2011.09 日本九州大学核工程系博士研究生 2005.09～2008.07 华南理工大学硕士研究生 2001.09～2005.07 华南理工大学大学本科工作经历 2023.09~至今哈尔滨工程大学核科学与技术学院教授 2015.06～2023.09 中山大学中法核工程与技术学院副教授 2012.04～2015.03 日本原子力研究开发机构（JAEA）大洗快堆研发中心博士研究员 2011.10～2012.03 日本九州大学核工程系学术研究员

研究领域

液态金属冷却快堆（钠堆、铅堆）技术核反应堆热工水力与安全反应堆严重事故分析

近期论文

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专利成果 [9] 成松柏，陈松徽，程辉. 一种静止液体中气泡迁移行为可视化实验系统.实用新型专利（申请号：202420877760X），2024. （实质审查中） [8] 成松柏，陈耀东，闫淼，崔蕾. 一种反应堆本体所在水池的自驱动式补水系统及补水方法. 发明专利（申请号：202311109042.4），2023. （实质审查中） [7] 程辉，成松柏，闫淼. 一种液流方向可控的流动液体中气泡迁移特性实验装置. 授权实用新型专利（ZL202221216951.9），2022. [6] 成松柏，区凯钧. 一种核反应堆严重事故下共晶反应实验系统. 发明专利（申请号：202211100292.7），2022. （实质审查中） [5] 成松柏，程辉，闫淼，李赵龙，张树成. 一种透明与非透明液体中气泡迁移特性测量实验系统. 发明专利（申请号：202211125759.3），2022. （实质审查中） [4] 成松柏，邓子健，程辉. 铅冷快堆过冷水与熔融铅合金相互作用压力特性实验系统. 授权实用新型专利（专利号：ZL 202121892719.2），2022. [3] 成松柏，程辉，陈松徽. 一种铅冷快堆加压水射流两相流动可视化实验系统. 授权实用新型专利（专利号：ZL202121892841.X），2022. [2] 成松柏，何利观，王健源，朱芳萌. 钠冷快堆严重事故时堆芯熔融物碎化行为的可视化实验系统. 授权发明专利 (专利号：ZL 201810834168.0), 2021. [1] 成松柏，林少鹏，潘梓毅，等. 一种钠冷快堆碎片床形成特性实验系统. 授权发明专利 (专利号：ZL 201610871371.6), 2018. 出版著作 [7] 成松柏，周文忠，郭京渝，谭少杰，王凯. 液态金属冷却反应堆燃料与材料基础. 北京：清华大学出版社，2024年. (in press) [6] 成松柏，陈啸麟，程辉. 液态金属冷却反应堆热工水力与安全分析基础（ISBN: 978-7-302-61359-6）. 北京：清华大学出版社，2022年. [5] S. Cheng, R. Xu. Safety of Sodium-cooled Fast Reactors: Particle-bed-related Phenomena in Severe Accidents (ISBN: 978-981-16-6115-0). Springer, 2021. [4] 成松柏，徐锐聪. 钠冷快堆严重事故中颗粒床相关现象机理研究（ISBN: 978-7-302-57675-4）. 北京：清华大学出版社，2021年. [3] 成松柏，程辉，陈啸麟，叶仪基. 铅冷快堆液态铅合金技术基础（ISBN: 978-7-302-56406-5）.北京：清华大学出版社，2020年. [2] 成松柏，王丽，张婷. 第四代核能系统与钠冷快堆概论（ISBN: 978-7-118-11485-0）. 北京：国防工业出版社，2018年. [1] H. Cheng, S. Cheng, S. Chen. Chapter 10 - Sodium Fast Reactors, in: Nuclear Power Reactor Designs: From History to Advances - Structures, Systems, and Components, ISBN 9780323998802, Academic Press, 2023. 发表论文 [75] Shaojie Tan, Shaoxiong Xia, Hui Cheng*, Songbai Cheng*. Numerical simulation of in-vessel steam explosion for China third-generation·PWR. Nuclear Engineering and Design, 424, 113258, 2024. [74] Haoran Huang, Zijian Deng, Songbai Cheng*, Jiayue Chen*. Systematic experimental investigation on pressure build-up characteristics of water jet injection into a molten LBE pool. Nuclear Science and Techniques, 2024. (in press) [73] Gen Jiang, Mou Wang, Kai Wang*, Songbai Cheng*. Review of the research on the scrubbing of fission products in liquid metal pool. Nuclear Engineering and Design, 421, 113075, 2024. [72] Bing Tan, Jiejin Cai*, Songbai Cheng*. Bubble characteristics on FeCrAl surface in subcooled boiling flow. Progress in Nuclear Energy, 169, 105108, 2024. [71] Mou Wang, Gen Jiang, Songbai Cheng*, Kai Wang*. Review of Fission Gas Release in Liquid Metal Reactor Fuel Cladding Failure Accident. Nuclear Engineering and Design, 419, 112981, 2024. [70] Ruicong Xu, Songbai Cheng*. From Debris Bed Formation to Self-Leveling Behaviors in Core Disruptive Accident of Sodium-cooled Fast Reactor. Nuclear Engineering and Design, 418, 112930, 2024. [69] Songhui Chen, Songbai Cheng*, Hui Cheng*. Study of bubble migration characteristics in downward flow under SGTR accidents of LFR with similarity experiments. Annals of Nuclear Energy, 199, 110363, 2024. [68] Jingyu Guo, Shaojie Tan, Kai Wang, Songbai Cheng*, Wenzhong Zhou*. Development of a fission gas release and swelling model for sodium-cooled fast reactor fuels. Nuclear Engineering and Design, 418, 112919, 2024. [67] Ruicong Xu, Songbai Cheng*, Yihua Xu, Yuecong Tan, Huaiqin Zhang. Effect of Coolant Boiling Induced by Accumulated Debris on Flow-Regime Characteristics of Debris Bed Formation Behavior for Sodium-Cooled Fast Reactor: Experimental and Modeling Study with Gas Injection. Progress in Nuclear Energy, 166, 104963, 2023. [66] Songbai Cheng*, Wenhui Jin, Xiaoxing Liu. Development of a clogging probability model in simplified geometry for fast reactor flow blockage analysis. Annals of Nuclear Energy, 195, 110177, 2024. [65] Ruicong Xu, Xiaoxing Liu*, Songbai Cheng*. Numerical Study of Debris Bed Formation Behavior for Severe Accident in Sodium-Cooled Fast Reactor by Using Least Square MPS-DEM Method. Nuclear Engineering and Design, 415, 112624, 2023. [64] Hui Cheng, Songhui Chen, Haoran Huang, Songbai Cheng*, Zichen Zhao*, Jiyun Zhao. Study on water jet penetration behavior in molten LBE during SGTR accident with simulant experiments. Nuclear Engineering and Design, 411, 112413, 2023. [63] Ruicong Xu, Songbai Cheng*. Characteristics and Mechanisms of Debris Bed Formation Behavior in Severe Accidents of Sodium-cooled Fast Reactor: Experimental and Modeling Studies. Applied Sciences, 13(11), 6329, 2023. [62] Wenhui Jin, Songbai Cheng*, Xiaoxing Liu. Experimental study on the mechanism of flow blockage formation in fast reactor. Nuclear Science and Techniques, 34, 84, 2023. [61] Songbai Cheng, Wenzhong Zhou*, Long Gu, Hongli Chen, Di Yun, Koji Morita, Hidemasa Yamano, Shripad T Revankar. Editorial: Experimental and Numerical Studies on Liquid Metal Cooled Fast Reactors. Frontiers in Energy Research, 11, 1140962, 2023. [60] Zijian Deng, Songbai Cheng*, Hui Cheng. Experimental investigation on pressure-buildup characteristics of a water lump immerged in a molten lead pool. Nuclear Science and Techniques, 34, 35, 2023. [59] Kai Wang, Inoue Junya, Chun-Yen Li, Songbai Cheng*, Koji Okamoto. Invariant aluminum CHF under electron beam irradiation conditions for downward-facing flow boiling. Applied Thermal Engineering, 220, 119810, 2023. [58] Hui Cheng, Shaojie Tan, Songbai Cheng*. Study on the effect of jet cross section shape on molten fuel fragmentation behavior with simulant experiments. Nuclear Engineering and Design, 400, 112077, 2022. [57] Kai Wang, Zhenhan Hong, Hui Liang, Inoue Junya, Songbai Cheng*, Koji Okamoto. Experimental investigation on the characteristics of bubble growth and slide on a downward-facing heater surface in flow boiling. International Journal of Thermal Sciences, 184, 108008, 2023. [56] S. Tan, Y. Zhong, H. Cheng*, S. Cheng*. Experimental investigation on the characteristics of molten lead-bismuth non-eutectic alloy fragmentation in water. Nuclear Science and Techniques, 33, 115, 2022. [55] R. Xu, S. Cheng*. Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-cooled Fast Reactor: Review of Experimental and Modeling Investigations. Science and Technology of Nuclear Installations, 2755471, 2022. [54] Z. Mai, Z. Zhao, H. Cheng*, S. Cheng*, J. Zhao. Numerical study on the release and migration behavior of fission gas in molten LBE. Frontiers in Energy Research, 10, 964841, 2022. [53] R. Xu, S. Cheng*. Experimental and Numerical Investigations on Molten-Pool Sloshing Motion for Severe Accident Analysis of Sodium-cooled Fast Reactor: A Review. Frontiers in Energy Research, 10, 893048, 2022. [52] R. Xu, S. Cheng*, Y. Xu, Y. Tan, H. Zhang. Investigations on flow-regime characteristics during debris bed formation behavior in sodium-cooled fast reactor by releasing high-temperature particles. Nuclear Engineering and Design, 395, 111866, 2022. [51] S. Li, S. Cheng*, W. Jin, X. Zeng, Y. Qin. Experimental investigation on sloshing motion in a liquid pool with binarily mixed-density solid particles. Annals of Nuclear Energy, 174, 109158, 2022. [50] H. Cheng, S. Cheng*, J. Wang*. Numerical study on the effect of jet cross section shape on the corium jet breakup behavior with lattice Boltzmann method. Frontiers in Energy Research, 10, 834237, 2022. [49] H. Cheng, Z. Mai, Y. Li, S. Cheng*. Fundamental experiment study on the fragmentation characteristics of molten lead jet direct contact with water. Nuclear Engineering and Design, 386, 111560, 2022. [48] R. Xu, S. Cheng*, S. Li, H. Cheng. Knowledge from recent investigations on sloshing motion in a liquid pool with solid particles for severe accident analyses of sodium-cooled fast reactor. Nuclear Engineering and Technology, 54(2): 589-600, 2022. [47] H. Cheng, J. Zhao*, S. Saito, S. Cheng*. Study on melt jet breakup behavior with nonorthogonal central-moment MRT color-gradient lattice Boltzmann method. Progress in Nuclear Energy, 136,103725, 2021. [46] S. Cheng*, Y. Zou, Y. Dong, H. Cheng, Y. Ye, X. Chen, Y. Chen. Experimental study on pressurization characteristics of a water droplet entrapped in molten LBE pool. Nuclear Engineering and Design, 378, 111192, 2021. [45] R. Xu, S. Cheng*. Review of the Molten-pool Sloshing Motion in case of Core Disruptive Accident: Experimental and Modeling Studies. Progress in Nuclear Energy, 133, 103647, 2021. [44] H. Cheng, X. Chen, Y. Ye, S. Cheng*. Systematic experimental investigation on the characteristics of molten lead-bismuth eutectic fragmentation in water. Nuclear Engineering and Design, 371, 110943, 2021. [43] S. Cheng*, Y. Dong, X. Chen, Y. Ye, Y. Chen. Experimental study on local fuel–coolant interaction in molten pool with different melts. Annals of Nuclear Energy, 149, 107760, 2020. [42] Y. Ye, X. Chen, S. Cheng*. Experimental study on melt-jet behavior during SFR core disruptive accidents using simulant materials. Annals of Nuclear Energy, 148, 107705, 2020. [41] H. Cheng, S. Cheng*, J. Zhao**. Study on corium jet breakup and fragmentation in sodium with a GPU-accelerated color-gradient lattice Boltzmann solver. International Journal of Multiphase Flow, 126, 103264, 2020. [40] Z. Xiong, S. Cheng*, R. Xu, Y. Tan, H. Zhang, Y. Xu. Experimental study on eutectic reaction between fuel debris and reactor structure using simulant materials. Annals of Nuclear Energy, 139, 107284, 2020. [39] S. Cheng*, W. Jin, Y. Qin, X. Zeng, J. Wen. Investigation of flow-regime characteristics in a sloshing pool with mixed-size solid particles. Nuclear Engineering and Technology, 52(5):925-936, 2020. [38] S. Cheng*, R. Xu, W. Jin, Y. Qin, X. Zeng, S. Li, K. Li. Experimental study on sloshing characteristics in a pool with stratified liquids. Annals of Nuclear Energy, 138, 107184, 2020. [37] S. Cheng*, X. Li, F. Liang, S. Li, K. Li. Study on sloshing motion in a liquid pool with non-spherical particles. Progress in Nuclear Energy, 117, 103086, 2019. [36] S. Cheng*, L. He, F. Zhu, J. Wang, R. Xu, H. Zhang, Y. Tan, Y. Xu. Experimental study on flow regimes in debris bed formation behavior with mixed-size particles. Annals of Nuclear Energy, 133: 283-296, 2019. [35] S. Cheng*, T. Zhang, C. Meng, T. Zhu, Y. Chen, Y. Dong, X. Chen, Y. Ye. A comparative study on local fuel-coolant interactions in a liquid pool with different interaction modes. Annals of Nuclear Energy, 132: 258-270, 2019. [34] Z. Xiong, S. Cheng*, Y. Sun, L. Huang, N. Wang, J. Wen. A simulated experimental study on eutectic reaction of core materials using Pb-Sn couple. Annals of Nuclear Energy, 131: 93-101, 2019. [33] S. Cheng*, L. He, J. Wang, F. Zhu, J. Cui. An experimental study on debris bed formation behavior at bottom-heated boiling condition. Annals of Nuclear Energy, 124:150-163, 2019. [32] S. Cheng*, S. Li, K. Li, T. Zhang. An experimental study on pool sloshing behavior with solid particles. Nuclear Engineering and Technology, 51(1):73-83, 2019. [31] S. Cheng*, S. Li, K. Li, T. Zhang, N. Zhang, X. Li, F. Liang. Prediction of flow-regime characteristics in pool sloshing behavior with solid particles. Annals of Nuclear Energy, 121:11-21, 2018. [30] T. Zhang, S. Cheng*, T. Zhu, C. Meng, X. Li. A new experimental investigation on local fuel-coolant interaction in a molten pool. Annals of Nuclear Energy, 120: 593-603, 2018. [29] S. Cheng*, T. Zhang, J. Cui, P. Gong, Y. Qian. Insight from Recent Experimental and Empirical-Model Studies on Flow-Regime Characteristics in Debris Bed Formation Behavior. Journal of Nuclear Engineering and Radiation Science, 4, 031003, 2018. [28] S. Cheng *, S. Li, K. Li, N. Zhang, T. Zhang. A two-dimensional experimental investigation on the sloshing behavior in a water pool. Annals of Nuclear Energy, 114: 66-73, 2018. [27] S. Cheng*, J. Cui, Y. Qian, P. Gong, T. Zhang, S. Wang, G. Jiang. An experimental investigation on flow-regime characteristics in debris bed formation behavior using gas-injection. Annals of Nuclear Energy, 112: 856-868, 2018. [26] S. Cheng*, P. Gong, S. Wang, J. Cui, Y. Qian, T. Zhang, G. Jiang. Investigation of Flow Regime in Debris Bed Formation Behavior with Non-Spherical Particles. Nuclear Engineering and Technology, 50(1): 43-53, 2018. [25] S. Cheng*, S. Wang, G. Jiang, J. Yu, Y. Qian, P. Gong, J. Cui. Development and analysis of a regime map for predicting debris bed formation behavior. Annals of Nuclear Energy, 109: 658-666, 2017. [24] S. Lin, S. Cheng*, G. Jiang, Z. Pan, H. Lin, S. Wang, L. Wang, X. Zhang, B. Wang. A two-dimensional experimental investigation on debris bed formation behavior. Progress in Nuclear Energy, 96:118-132, 2017. [23] S. Cheng, H. Chen, X. Zhang*. CFD analysis of flow field in a 5 × 5 rod bundle with multi-grid. Annals of Nuclear Energy, 99:464-470, 2017. [22] S. Cheng*, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita. A numerical study on local fuel-coolant interactions in a simulated molten fuel pool using the SIMMER-III code. Annals of Nuclear Energy, 85:740-752, 2015. [21] S. Cheng*, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita. The Effect of coolant quantity on local fuel-coolant interactions in a molten pool. Annals of Nuclear Energy, 75: 20-25, 2015. [20] S. Cheng*, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita. SIMMER-III Analyses of Local Fuel-Coolant Interactions in a Simulated Molten Fuel Pool: Effect of Coolant Quantity. Science and Technology of Nuclear Installations, 2015, 964327, 2015. [19] S. Cheng*, H. Tagami, H.Yamano, T. Suzuki, Y. Tobita, S. Takeda, S. Nishi, T. Nishikido, B. Zhang, T. Matsumoto, K. Morita. An Investigation on debris bed self-leveling behavior with non-spherical particles. Journal of Nuclear Science and Technology, 51(9): 1096 - 1106, 2014. [18] S. Cheng*, H. Tagami, H.Yamano, T. Suzuki, Y. Tobita, Y. Nakamura, S. Takeda, S. Nishi, B. Zhang, T. Matsumoto, K. Morita. Experimental study and empirical model development for self-leveling behavior of debris bed using gas-injection. Mechanical Engineering Journal, 1(4), TEP0022, 2014. [17] S. Cheng*, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita. An Experimental study on local fuel-coolant interactions by delivering water into a simulated molten fuel pool. Nuclear Engineering and Design, 275:133-141, 2014. [16] S. Cheng*, H. Tagami, H.Yamano, T. Suzuki, Y. Tobita, B. Zhang, T. Matsumoto, K. Morita. Evaluation of debris bed self-leveling behavior: A Simple empirical approach and its validations. Annals of Nuclear Energy, 63(1):188-198, 2014. [15] S. Cheng*, H. Yamano, T. Suzuki, Y. Tobita, Y. Gondai, Y. Nakamura, B. Zhang, T. Matsumoto, K. Morita. An Experimental investigation on self-leveling behavior of debris beds using gas-injection. Experimental Thermal and Fluid Science, 48: 110-121, 2013. [14] S. Cheng*, H. Yamano, T. Suzuki, Y. Tobita, Y. Nakamura, B. Zhang, T. Matsumoto, K. Morita. Characteristics of self-leveling behavior of debris beds in a series of experiments. Nuclear Engineering and Technology, 45(3): 323-334, 2013. [13] S. Cheng*, H. Yamano, T. Suzuki, Y. Tobita, Y. Nakamura, B. Zhang, T. Matsumoto, K. Morita. Empirical correlations for predicting the self-leveling behavior of debris bed. Nuclear Science and Techniques, 24(1), 010602, 2013. [12] S. Cheng*, Y. Tanaka, Y. Gondai, T. Kai, B. Zhang, T. Matsumoto, K. Morita, K. Fukuda, H.Yamano, T. Suzuki, Y. Tobita. Experimental studies and empirical models for the transient self-leveling behavior in debris bed. Journal of Nuclear Science and Technology, 48(10): 1327-1336, 2011. [11] S. Cheng*, D. Hirahara, Y. Tanaka, Y. Gondai, B. Zhang, T. Matsumoto, K. Morita, K. Fukuda, H. Yamano, T. Suzuki, Y.Tobita. Experimental Investigation of Bubbling in Particle Beds with High Solid Holdup. Experimental Thermal and Fluid Science, 35(2): 405-415, 2011. [10] S. Cheng, G. Chen*, Q. Chen, X. Xiao. Research on 3D Dynamic Visualization Simulation System of Toxic Gas Diffusion Based on Virtual Reality Technology. Process Safety and Environmental Protection, 87(3): 175-183, 2009. [9] Xiaoxing Liu, Yihua Xu, Kai Wang, Songbai Cheng, Lili Tong*. Study on bubble dynamics in sodium using three-dimensional MPS method. Nuclear Engineering and Design, 416, 112810, 2024. [8] Shaojie Tan, Songbai Cheng, Kai Wang, Xiaoxing Liu, Hui Cheng*, Jun Wang*. The development of micro and small modular reactor in the future energy market. Frontiers in Energy Research, 11, 1149127, 2023. [7] J. Guo, S. Cheng, K. Wang*, W. Zhou*. Extended development of a fission gas release behavior model inside spherical fuel grains for LWR reactors. Applied Sciences, 13(18), 10421, 2023. [6] B. Qiu, X. Liu, K. Wang*, S. Cheng, Z. Hong, K. Okamoto. Effects of surface alteration on CHF related to IVR accident scenarios: A review. Progress in Nuclear Energy, 159, 104653, 2023. [5] J. Lv, X. Liu*, K. Wang, S. Cheng, L. Tong*. Numerical study of gas-injection induced pool sloshing behavior using MPS method. International Journal of Advanced Nuclear Reactor Design and Technology, 4(3): 147-155, 2022. [4] Y. Xu, R. Xu, H. Cheng*, X. Liu*, S. Cheng. Numerical simulation of jet breakup phenomenon during severe accident of sodium-cooled fast reactor using MPS method. Annals of Nuclear Energy, 172, 109087, 2022. [3] H. Tagami*, S. Cheng, Y. Tobita, K. Morita. Model for particle behavior in debris bed. Nuclear Engineering and Design, 328: 95-106, 2018. [2] K. Morita*, T. Matsumoto, S. Nishi, T. Nishikido, S. Cheng, H. Tagami, T. Suzuki, Y. Tobita. A New Empirical Model for Self-Leveling Behavior of Cylindrical Particle Beds. Journal of Nuclear Science and Technology, 53(5):713-725, 2016. [1] M. Zheng, G. Chen*, S. Cheng. JC-Integral Fracture Parameter Analysis and Application for Double-Layer High-Temperature Components. Engineering Failure Analysis, 18(1): 52-60, 2011.

学术兼职

[1] 现为中国核学会会员（曾为日本原子力学会和日本机械学会会员）； Member of the Chinese Nuclear Society (Previouly member of the Atomic Energy Society of Japan and the Japan Society of Mechanical Engineering); [2] 中国能源学会等学术组织专家委员会委员； Member of the Expert Committee of academic organizations such as China Energy Society; [3] 国际期刊Frontiers in Energy Research，Frontiers in Nuclear Engineering，Nuclear Science，International Journal of Advanced Nuclear Reactor Design and Technology等编委或青年编委； Member of editorial board (or young editorial board) of international journals including Frontiers in Energy Research, Frontiers in Nuclear Engineering, Nuclear Science, International Journal of Advanced Nuclear Reactor Design and Technology; [4] SCI期刊Frontiers in Energy Research (Nuclear energy section)学术专刊“Experimental and Numerical Studies on Liquid Metal Cooled Fast Reactors”、国际期刊International Journal of Advanced Nuclear Reactor Design and Technology学术专刊“Challenges and recent progress in liquid metal-cooled fast reactors” 、SCI期刊Applied Science学术专刊“Security Analysis of Nuclear Energy and Nuclear Reactor Thermal Hydraulics”发起人和编委，国际期刊Frontiers in Nuclear Engineering学术专刊“Artificial Intelligence in Advanced Nuclear Reactor Design”编委； Several academic special issues launched including the special issue "Experimental and Numerical Studies on Liquid Metal Cooled Fast Reactors" in Frontiers in Energy Research (Nuclear energy section), the special issue "Challenges and recent progress in liquid metal-cooled fast reactors " in International Journal of Advanced Nuclear Reactor Design and Technology, the special issue ""Security Analysis of Nuclear Energy and Nuclear Reactor Thermal Hydraulics" in Applied Science, and the special issue "Artificial Intelligence in Advanced Nuclear Reactor Design" in Frontiers in Nuclear Engineering; [5] International Symposium on Thermal Hydraulics and Safety of Advanced Nuclear Energy Systems系列国际学术会议发起/创办人； Initiator of International Symposium on Thermal Hydraulics and Safety of Advanced Nuclear Energy Systems; [6] Nuclear Engineering and Design, Annals of Nuclear Energy，Progress in Nuclear Energy, Nuclear Science and Techniques, Journal of Nuclear Science and Technology，Nuclear Engineering and Technology, ASME-Journal of Nuclear Engineering and Radiation Science, Process Safety and Environmental Protection，Science and Technology of Nuclear Installations，Journal of Energy and Power Engineering，Journal of Thermal Science，Acta Mechanica Sinica，International Journal of Electrical Power and Energy Systems等专业领域国际期刊审稿人； Reviewer of international journals such as Nuclear Engineering and Design, Annals of Nuclear Energy, Progress in Nuclear Energy, Nuclear Science and Techniques, Journal of Nuclear Science and Technology, Nuclear Engineering and Technology, ASME-Journal of Nuclear Engineering and Radiation Science, Process Safety and Environmental Protection, Science and Technology of Nuclear Installations, Journal of Energy and Power Engineering, Journal of Thermal Science, etc; [7] Track/Session Chair of 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), 25th International Conference on Nuclear Engineering (ICONE-25), 12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), 9th International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2018), 4th International Symposium on Heat Transfer and Energy Conservation, 2015 International Symposium on Severe Accidents Simulation and Experiments for Nuclear Power Plants, etc; [8] 国家科技专家库、中国博士后科学基金、广东省自然科学基金、北京市自然科学基金、山东省科技专家库、广州市科技专家库、广东省科技人才服务中心、广州生产力促进中心、广东省环境应急“辐射污染防治”专家库、珠海市环境影响评价专家库等专家; Expert of seveal expert database including National Science and Technology expert Database, China Postdoctoral Science Foundation, Guangdong Natural Science Foundation, Beijing Natural Science Foundation, Shandong Province Science and Technology Expert Database, Guangzhou Science and Technology Expert Database, Guangdong Science and Technology Personnel Service Center, Guangzhou Productivity Promotion Center, Guangdong environmental emergency "radiation pollution prevention" experts, Zhuhai environmental impact assessment expert database.

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