刘晓晶 研究员
所在系所核科学与工程学院
办公电话
通讯地址上海交大机械与动力工程学院A楼328室
电子邮件xiaojingliu@sjtu.edu.cn
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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—现在 上海交通大学/核科学与工程学院 副教授，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****

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 2020-2022 国家自然科学基金优秀青年基金“数值反应堆多物理耦合”，负责人
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****奖励计划优秀青年教师（C类）
上海交通大学SMC-晨星青年****奖励计划优秀青年教师（B类）