刘晓晶（上海交大教授）的个人简介
刘晓晶，上海交通大学核科学与工程学院党支部书记，副教授，研究反应堆热工水力分析; 超临界水冷堆设计及分析; 子通道程序与核热耦合程序开发;不确定性分析与程序验证。
学习简历
2006―2010上海交通大学核科学与工程博士
2004―2006 上海交通大学 核科学与工程 硕士
2000―2004燕山大学机械工程 学士
工作简历
2007―2008慕尼黑工业大学访问学者
2010―2013 上海交通大学/核科学与工程学院 助理研究员
2012―2013德国卡尔斯鲁厄理工学院（KIT）博士后
2013―上海交通大学/核科学与工程学院副教授
研究方向
反应堆热工水力分析; 超临界水冷堆设计及分析; 子通道程序与核热耦合程序开发;不确定性分析与程序验证
科研项目
2013D2014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
2012D2014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
2012D2014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
2011D2015 国家重大专项 “核电关键软件自主化技术研究堆芯物理-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
2011D2014 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
2012D2014 教育部高校博士学科点专项科研基金（新教师类）“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
2011D2012 上海核工程研究设计院国家科技重大专项外协子课题“方形旁支管声共振基础试验研究”，负责人
2010―2011 IAEA国际合作项目“Heat Transfer Behavior and Thermo-hydraulics Code Testing for Supercritical Water-Cooled Reactors (SCWRs)”，负责人
2010D2012 IAEA国际合作项目“Heat Transfer Behavior and Thermo-hydraulics Code Testing for Supercritical Water-Cooled Reactors (SCWRs)” Renewal，负责人
2011D2012 中广核校企合作项目“超临界水堆方案计算分析研究”，负责人
代表性论文论著
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,262,499u2013509.(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 44,40u201349.(SCI)
Yang, T.,Liu, X.J.and Cheng, X.(2011): Optimization of multilayer fuel assemblies for supercritical water-cooled reactors with mixed neutron spectrum, Nuclear Engineering and Design, published online.(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., Cheng, X. (2008): Steady-state thermal-hydraulic analysis of SCWR assembly, Frontiers of Energy and Power Engineering in China, 2(4), 475-478. (EI)
Liu, X.J., Kerner, A. and Schaefer A.(2008), Using statistical sensitivities for adaptation in a Thermo-hydraulic simulation, Transactions of the American Nuclear Society, 98, 451(EI)
