个人信息
科学研究
教育教学
社会兼职
论著成果
荣誉奖励

成松柏

Cheng Song Bai

部门：核科学与技术学院

学科：核科学与技术

职务：

职称：教授

指导资格：博士生导师

电话： -

传真：

邮箱： chengsongbai@hrbeu.edu.cn

邮编： 150001

地址：黑龙江省哈尔滨市南通大街哈尔滨工程大学31号楼

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/通讯作者已发表约70篇SCI国际期刊论文，以第一发明人申请/授权约10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6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、Energy Research Journal、Nuclear Science、International Journal of Advanced Nuclear Reactor Design and Technology（JANDT）等副主编/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

研究方向

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

承担项目

2024~2027 负责人，中核领创项目“一体化快堆创新的联通盒内式自然循环设计的关键现象研究”
2024~2024 负责人，中央高校基本科研业务费项目“高温液态金属射流在冷却剂中碎化特性及蒸汽爆炸机理研究”
2024~2025 负责人，先进核能技术设计与安全教育部重点实验室开放基金重点项目“铅铋快堆液态铅铋中气泡迁移行为研究”
2022～2023 负责人，国家电投集团科学技术研究院有限公司横向项目“铅冷快堆热工水力实验数据库搭建（一期）采购”
2022～2023 负责人，中国散裂中子源科学中心横向项目“CSNS靶站TMR异常工况热分析校核”
2022～2023 负责人，2022年度珠海市珠港澳科技创新合作项目“铅铋冷却快堆高温熔融铅铋与过冷水相互作用研究”
2022～2024 负责人，广东省自然科学基金面上项目“基于实验与LBM方法的静止与流动熔融铅铋中气泡迁移特性研究”
2021～2023 负责人，中广核研究院有限公司横向项目“铅铋快堆多场多组分分析软件开发与验证技术支持采购”
2020～2022 负责人，广东省科技计划项目国际科技合作项目“铅铋冷却快堆高温熔融铅铋与过冷水相互作用研究”
2020～2020 负责人，中广核研究院有限公司横向项目“氦氙混合气体热物性数据采购”
2018～2020 负责人，广东省科技计划项目“快堆严重事故中颗粒床相关现象机理研究”
2017～2020 负责人，广州市科技计划项目“钠冷快中子反应堆堆芯解体事故时考虑核衰变条件下碎片床形成机理研究”
2015～2017 负责人，高校基本科研业务费重大项目培育和新兴交叉学科培育计划项目“钠冷快堆堆芯解体事故时熔融燃料池内局部燃料-冷却剂相互作用可视化实验及数值模拟研究”
2016～2017 负责人，中山大学2016年研究生课程建设项目优秀教材建设“第四代核能系统和钠冷快中子反应堆”
2015～2020 负责人，受中山大学“百人计划二期”资助，开展“先进核能技术（液态金属冷却快堆）”相关研究
2012～2015 主要参与者，日本原子力研究开发机构课题“钠冷快堆堆芯解体事故时熔融燃料池内局部燃料-冷却剂相互作用实验及SIMMER-III数值模拟研究”
2010～2012 主要参与者，日本原子力研究开发机构-九州大学联合研究课题“钠冷快堆堆芯解体事故时燃料粒子碎片床运动特性相关基础研究”

学术交流

[25] 2024 SJTU – KAIST – NTHU – KU – HEU Joint Summer School on Nuclear Science and Technology， Ito Campus, Kyushu University，Fukuoka, Japan, Aug.5th- 9th, 2024
[24] 先进核能技术全国重点实验室2024年学术年会，四川成都，2024年4月16日-20日
[23] 2023年先进核能技术设计与安全教育部重点实验室学术委员会会议暨学术年会，湖南衡阳，2023年12月14日~15日
[22] 中国核学会核反应堆热工流体力学分会第三届学术年会，陕西西安，2023年9月25日~27日
[21] 2023年核动力厂严重事故管理研讨会，四川成都，2023年9月20日~22日
[20] 30th International Conference on Nuclear Engineering (ICONE30), 日本京都，2023年5月21日~26日
[19]国家能源核电软件重点实验室2022-2023 年学术交流会暨学术年会，广东珠海，2023年6月6日~8日
[18] International Symposium on Thermal Hydraulics and Safety of Advanced Nuclear Energy Systems 2022，中国珠海，2022年11月4日~5日
[17] 12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Qingdao, China, Oct 14-18, 2018
[16] 9th International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2018), Heilongjiang, China, July 9-11 2018
[15] 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Xi'an, Shaanxi, China, September 3-8, 2017
[14] 25th International Conference on Nuclear Engineering (ICONE-25), Shanghai, China, July 2-6, 2017
[13] 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017), Fukui and Kyoto, Japan, April 24-28, 2017
[12] 8th International Symposium on Symbiotic Nuclear Power Systems for 21st Century(ISSNP 2016), Chengdu, China, September 26-28, 2016
[11] 23rd International Conference on Nuclear Engineering (ICONE23), Chiba, Japan, May 17 - 21, 2015
[10] 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10), Ginowan, Japan, Dec 14-18, 2014
[9] International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2014), Jeju, Korea, Aug 24-28, 2014
[8] 22nd International Conference on Nuclear Engineering (ICONE-22), Prague, Czech Republic, July 7-11, 2014
[7] International Symposium on Symbiotic Nuclear Power Systems for 21st Century (ISSNP 2013), Beijing, China, November 22-24, 2013
[6] International Conference on Power Engineering 2013 (ICOPE 2013), Wuhan, China, Oct 23-27, 2013
[5] 21st International Conference on Nuclear Engineering (ICONE-21), Chengdu, China, July 29-August 2, 2013
[4] 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8), Beppu, Japan, Dec 9-12, 2012
[3] 4th International Symposium on Heat Transfer and Energy Conservation (ISHTEC2012), Guangzhou, China, Jan. 6-9, 2012
[2] 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010
[1] 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010

招生信息

招收博士研究生、硕士研究生及本科毕业设计；
招生方向包括但不限于液态金属反应堆（钠堆、铅堆）等先进核能系统热工水力、安全与严重事故分析（含实验与数值模拟）。

本科生授课课程

传热学
核电厂系统与设备
核动力装置用泵与阀门

研究生授课课程

反应堆安全
热机
高等反应堆工程
核能系统安全与分析
液态金属冷却快堆热工水力与安全

实践性教学

教学研究课题

2021.07-2021.12 中山大学校级研究生联合培养基地项目建设“中山大学-国家电投集团科学技术研究院有限公司研究生联合培养基地”

2020.01-2021.12 中山大学校级专业学位研究生教育综合改革项目“中法核能精英工程师培养模式的实践、评估及优化 ”

2018.07-2020.06 中山大学校级本科教学改革研究项目“未来先进核反应堆与当前压水堆技术在核工程类专业教育中的定位及思考”

社会兼职

[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，Energy Research Journal，Nuclear Science，International Journal of Advanced Nuclear Reactor Design and Technology等副主编/编委或青年编委；
Member (including associate editor) of editorial board (or young editorial board) of international journals such as Frontiers in Energy Research, Frontiers in Nuclear Engineering, Energy Research Journal, 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.

专利成果

[11] 成松柏，刘振弘，谭冰. 一种透明液体与非透明液体中颗粒群流动堵塞实验系统. 发明专利（申请号：202411583556.8），2024. （实质审查中）
[10] 陈耀东，成松柏，闫淼. 池式反应堆的冷却系统及反应堆系统. 发明专利（申请号：CN202211309979.1），2022. （实质审查中）
[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（ISBN: 978-7-302-67043-8）. 北京：清华大学出版社，2024年.
[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

[78] Zhenhong Liu, Songbai Cheng*, Wanai Li*, Wenhui Jin. Review of Researches on Flow Blockage Accident in Liquid-Metal-Cooled Reactor. Progress in Nuclear Energy, 176, 105372, 2024.

[77] Kuanghan Deng, Bing Tan*, Songbai Cheng*, Rulei Sun, Haoliang Ren. Investigating bubble dynamics on silicon carbide surfaces during flow boiling. Case Studies in Thermal Engineering, 60, 104807, 2024.

[76] Jingyu Guo, Mou Wang, Gen Jiang, Weiqi Cheng, Yubin Lin, Kai Wang*, Songbai Cheng*, Shaojie Tan, Wenzhong Zhou. Investigation of the Fission Gas Release and Grain Boundary Percolation in Oxide Fuels: A COMSOL Multiphysics-based Study. Nuclear Engineering and Design, 427, 113400, 2024.
[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.

荣誉

[5] 2023 国际期刊Nuclear Engineering and Technology优秀审稿人
2023 Outstanding Reviewer of the Nuclear Engineering and Technology(NET) journal
[4] 2023 中山大学，中山大学优秀硕士学位论文指导教师（2023）
2023 Sun Yat-sen University, Advisor of Excellent Master's Thesis , Sun Yat-sen University (2023)

[3] 2023 核反应堆系统设计技术重点实验室学术年会（2023），优秀会议论文三等奖，论文题目：水在熔融铅铋共晶合金中射流行为的模拟实验研究，获奖学生：陈松徽
2023 Annual Academic Conference of Key laboratory of Nuclear Reactor System Design Technology (2023), third prize of excellent conference paper, paper title: Simulated experimental study of water jet behavior in molten Lead bismuth eutectic alloy, student winner: Chen Songhui

[2] 2022 中山大学，指导本科毕业论文，中山大学优秀本科毕业论文（2022），获奖学生：闫淼
2022 Sun Yat-sen University, Supervision of Undergraduate Thesis, Excellent Undergraduate Thesis of Sun Yat-sen University (2022), Student Winner: Yan Miao

[1] 2014 日本机械学会(JSME)，第22回原子力工学国际会议(ICONE-22)，优秀论文，获奖者：成松柏

2014 Japan Society of Mechanical Engineering (JSME), 22nd International Conference on Nuclear Engineering (ICONE-22), Outstanding paper, Winner: Cheng Songbai

奖励

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