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刘晓晶 研究员
所在系所：核科学与工程学院 |
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
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
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
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)
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
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)
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）
(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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