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)