教授

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刘晓晶

研究员

所在系所:核科学与工程学院 
办公电话:021-34207121 
通讯地址:上海交通大学机械与动力工程学院A楼328室                      
电子邮件:xiaojingliu@sjtu.edu.cn 

教育背景
2006.9—2010.1 上海交通大学 核科学与工程 博士
工作经历

2010—2013 上海交通大学/核科学与工程学院 助理研究员 
2013—2018 上海交通大学/核科学与工程学院 副教授,博士生导师

2018—现在  上海交通大学/核科学与工程学院 研究员,博士生导师

出访及挂职经历
2012—2013 德国卡尔斯鲁厄理工学院(KIT) 博士后 
2007—2008 德国慕尼黑工业大学(TUM) 访问学者
研究方向
核反应堆热工水力安全
先进核能系统研发
数值反应堆技术
科研项目
2017-2018 装备预研教育部联合青年人才基金 “海洋核动力数值反应堆耦合技术”,负责人
2017-2020 上海市科技创新计划 “超临界流体流动传热特性研究及模型开发”, 负责人
2013―2014 中科院上海应用物理研究所合作项目“RELAP5改造中的实验验证方案研究”,负责人 
2012―2014 核能开发项目(欧盟FP7计划合作项目)“堆内超临界辐照实验回路设计技术研究”,课题二负责人 
2012―2014 国家自然科学基金项目“超临界区域流体传热模化理论及验证方法研究”,负责人 
2012―2014 教育部高校博士学科点专项科研基金“超临界水堆条件下流动传热数值模型评价方法的研究”,负责人 
2011―2015 国家重大专项子课题“堆芯物理-热工设计及系统安全分析软件包研发的工作参与 (1)-热工安全及棒束内流动和传热行为验证技术研究”,负责人 
2011―2014 上海市自然科学基金项目“混合中子能谱超临界水堆堆芯分析方法及性能研究”,负责人 
2011―2012 国家重大专项子课题“IVR方案中提高自然循环能力分析和严重事故序列研究”,负责人 
2011―2012 国家重大专项子课题“GASFLOW程序二次开发安全壳热工特性分”,负责人 
2011―2012 国家重大专项子课题“方形旁支管声共振基础试验研究”,负责人 
2010―2012 国际合作项目“Heat Transfer Behavior and Thermo-hydraulics Code Testing for Supercritical Water-Cooled Reactors (SCWRs)” Renewal,负责人 
2010—2011 国际合作项目“Heat Transfer Behavior and Thermo-hydraulics Code Testing for Supercritical Water-Cooled Reactors (SCWRs)”,负责人
代表性论文专著
Liu X.J., Ren S.,Cheng X.(2017),Development of a transverse mixing model for large scale impulsion phenomenon in tight lattice,Annals of Nuclear Energy,2017,101:159~165.(SCI)
Liu, X. J. ,Sun, C.,Wang, Z. D.,et al.(2016),Preliminary study to improve the performance of SCWR-M during loss-of-flow accident, Nuclear Engineering and Design, 2016, 307:431-444.(SCI)
Liu, X.J., Cheng, X.(2015), Sub-channel/system coupled code development and its application to SCWR-FQT loop, Nuclear Engineering and Design,2015,285: 39-47.(SCI)
Liu, X.J., Scarpelli, N.(2015), Development of a sub-channel code for liquid metal cooled fuel assembly, Annals of Nuclear Energy, 2015,77: 425-435 .(SCI)
Liu, X.J., Schaefer A. (2013).Improvement of ATHLET modelling capability for asymmetric natural circulation phenomenon using uncertainty and sensitivity measures,Annals of Nuclear Energy,62,471-482.(SCI) 
Liu, X.J., Yang, T. and Cheng, X(2013).Development and assessment of a sub-channel code applicable for trans-critical transient of SCWR, Nuclear Engineering and Design,262,499–509.(SCI) 
Liu, X.J., Yang, T. and Cheng, X (2013).Multi-layer fuel assembly design proposal for supercritical water cooled reactor, Progress in Nuclear Energy 67, 82-87.(SCI) 
Liu, X.J., Yang, T. and Cheng, X(2013).Thermal-hydraulic analysis of flow blockage in a supercritical water-cooled fuel bundle with sub-channel code, Annals of Nuclear Energy,59,194-203.(SCI) 
Liu X.J.,Fu S.W., Xu Z.H. et al.(2013).LOCA analysis of SCWR-M with passive safety system, Nuclear Engineering and Design,259,187-197.(SCI) 
Fu S.W., Liu X.J., Zhou C.et al.(2012).Modification and application of the system analysis code ATHLET to trans-critical simulations, Annals of Nuclear Energy 44,40–49.(SCI) 
Yang, T.,Liu, X.J.and Cheng, X.(2012).Optimization of multilayer fuel assemblies for supercritical water-cooled reactors with mixed neutron spectrum, Nuclear Engineering and Design,249,159-165.(SCI) 
Liu, X.J., Kerner, A. and Schaefer, A. (2010).Using statistical sensitivities for adaptation of a best-estimate thermo-hydraulic simulation model, Nuclear Engineering and Design, 240(10), 3413-3420. (SCI) 
Liu, X.J., Cheng, X. (2010): Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core, Progress in Nuclear Energy, 52(7), 640-647.(SCI) 
Liu, X.J., Yang, T. and Cheng, X. (2010).Core and sub-channel analysis of SCWR with mixed spectrum Core, 2010, Annals of Nuclear Energy, 37(12), 1674-1682.(SCI) 
Liu, X.J., Cheng, X. (2009).Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly, Annals of Nuclear Energy, 36, 28-36. (SCI) 
Liu, X.J., Cheng, X. (2009). Core and sub-channel evaluation of a thermal SCWR, Nuclear Engineering and Technology, 41(5), 677-690. (SCI) 
Cheng, X., Liu, X.J. and Yang, Y. H.(2008). A mixed core for supercritical water-cooled reactor, Nuclear Engineering and Technology, 40(2), 117-126.(SCI)
教学工作
1、课程名称:核工程管理 
授课对象:本科生 
学时数:36 
学分:2.0 
2、核反应堆热工水力 
授课对象:本科生 
学时数:54 
学分:3.0 
3、课程名称:核反应堆工程 
授课对象:本科生 
学时数:36 
学分:2 
4、课程名称:核能系统管理与经济分析 
授课对象:本科生 
学时数:36 
学分:2
学术兼职
Editorial Advisory Board member: Nuclear Engineering and Design(SCI) 
Guest Editor: Nuclear Engineering and Design(SCI) 
Member: American Nuclear Society 
会员:中国核学会/上海市核学会 
Director and local organizer: Joint SJTU-IAEA Course on Science and Technology of SCWRs, Shanghai, 2013. 
Invited lecturer: IAEA Course on Science and Technology of Supercritical Water Cooled Reactors,2011/2013. 
Assistant Chair of TPC: 8th Int.Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-8) 
TPC member: 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-8) 
TPC member: 9th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-9) 
TPC member: 10th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-10) 
Session Chair: International Workshop on Nuclear Safety and Severe Accidents (NUSSA) 
Session Chair: 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-8) 
Session Chair: 9th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-9) 
Session Chair: 10th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-10) 
Session Chair: 19th Pacific Basin Nuclear Conference(PBNC-2014)
荣誉奖励
Outstanding Contribution Award, 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety 
(NUTHOS-8),October 10-14 2010,Shanghai,China. 
Best Paper Award, 9th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-9) 
September,9-13 2012,Kaohsiung,Taiwan. 
上海交通大学2011年度教工考核优秀 
上海交通大学2013年度教工考核优秀 
上海交通大学2013年度聘期考核优秀 
上海交通大学SMC-晨星青年学者奖励计划优秀青年教师(C类) 
上海交通大学SMC-晨星青年学者奖励计划优秀青年教师(B类)

地址:中国·上海市闵行区东川路800号 200240

网址::http://nsse.sjtu.edu.cn

电话:021-34205182 传真:021-34205182

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