學(xué)習(xí)簡(jiǎn)歷
2006—2010上海交通大學(xué)核科學(xué)與工程博士
2004—2006 上海交通大學(xué) 核科學(xué)與工程 碩士
2000—2004燕山大學(xué)機(jī)械工程 學(xué)士
工作簡(jiǎn)歷
2007—2008慕尼黑工業(yè)大學(xué)訪問(wèn)學(xué)者
2010—2013 上海交通大學(xué)/核科學(xué)與工程學(xué)院 助理研究員
2012—2013德國(guó)卡爾斯魯厄理工學(xué)院（KIT）博士后
2013—上海交通大學(xué)/核科學(xué)與工程學(xué)院副教授
研究方向
反應(yīng)堆熱工水力分析; 超臨界水冷堆設(shè)計(jì)及分析; 子通道程序與核熱耦合程序開發(fā);不確定性分析與程序驗(yàn)證
科研項(xiàng)目
2013―2014中科院上海應(yīng)用物理研究所合作項(xiàng)目“RELAP5改造中的實(shí)驗(yàn)驗(yàn)證方案研究”，負(fù)責(zé)人
2012―2014核能開發(fā)項(xiàng)目（歐盟FP7計(jì)劃合作項(xiàng)目）“堆內(nèi)超臨界輻照實(shí)驗(yàn)回路設(shè)計(jì)技術(shù)研究”，課題二負(fù)責(zé)人
2012―2014國(guó)家自然科學(xué)基金項(xiàng)目“超臨界區(qū)域流體傳熱�；碚摷膀�(yàn)證方法研究”，負(fù)責(zé)人
2011―2015 國(guó)家重大專項(xiàng) “核電關(guān)鍵軟件自主化技術(shù)研究堆芯物理-熱工設(shè)計(jì)及系統(tǒng)安全分析軟件包研發(fā)的工作參與 (1)-熱工安全及棒束內(nèi)流動(dòng)和傳熱行為驗(yàn)證技術(shù)研究”，負(fù)責(zé)人
2011―2014 上海市自然科學(xué)基金項(xiàng)目“混合中子能譜超臨界水堆堆芯分析方法及性能研究”，負(fù)責(zé)人
2012―2014 教育部高校博士學(xué)科點(diǎn)專項(xiàng)科研基金（新教師類）“超臨界水堆條件下流動(dòng)傳熱數(shù)值模型評(píng)價(jià)方法的研究”，負(fù)責(zé)人
2011―2012 上海核工程研究設(shè)計(jì)院國(guó)家科技重大專項(xiàng)外協(xié)子課題“方形旁支管聲共振基礎(chǔ)試驗(yàn)研究”，負(fù)責(zé)人
2010—2011 IAEA國(guó)際合作項(xiàng)目“Heat Transfer Behavior and Thermo-hydraulics Code Testing for Supercritical Water-Cooled Reactors (SCWRs)”，負(fù)責(zé)人
2010―2012 IAEA國(guó)際合作項(xiàng)目“Heat Transfer Behavior and Thermo-hydraulics Code Testing for Supercritical Water-Cooled Reactors (SCWRs)” Renewal，負(fù)責(zé)人
2011―2012 中廣核校企合作項(xiàng)目“超臨界水堆方案計(jì)算分析研究”，負(fù)責(zé)人
代表性論文論著
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)
