2006-2010, Shanghai Jiao Tong University, Doctor
2004-2007, Shanghai Jiao Tong University, Master
2000-2004, Yanshan University, Bachelor

2007-2008 Visiting Scientist, ISaR Institute for Safety and Reliability at the Technical University Munich, Germany
2012-2013 Postdoctoral Researcher, Karlsruhe Institute of Technology (KIT), Germany.
2010-2013 Assistant Professor,School of Nuclear Science and Engineering, Shanghai Jiao Tong University
2013-2018 Associate Professor,School of Nuclear Science and Engineering, Shanghai Jiao Tong University
2018-present Professor,School of Nuclear Science and Engineering, Shanghai Jiao Tong University

Nuclear Thermal Hydraulics
Nuclear Safety
Advanced Nuclear Reactor
Code Development and V&V

1 PI, National Natural Science Foundation of China, Development of scaling method for heat transfer in supercritical fluid (51106097 25), 2012.01-2014.12
2 PI, National Natural Science Foundation of Shanghai, Core design analysis for mixed spectrum supercritical water cooled reactor (11ZR1416900) 2011.04-2014.03
3 PI, Doctoral Fund of Ministry of Education of China, Evaluation method for thermal hydraulic models in supercritical fluid (20110073120045), 2012.01-2014.12
4 PI, Cooperation between EU and China in nuclear: Supercritical water reactor - fuel qualification test (SCWR-FQT), 2012.01-2014.12
5 PI, Key Basic Research of the Ministry of Science and Technology China, COSINE code development for thermal hydraulic and neutronic analysis and validation techniques (2011ZX06004-024-02-01-03/2011ZX06004-024-07-01-03), 2011.01-2015.12
6 PI, IAEA CRP project, Heat Transfer and Flow Stability at Supercritical Pressure conditions and Its Applications to SCWRs, 2011.01-2013.12
7 PI, IAEA CRP project, Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to SCWR, 2015.01-2017.12
8 PI, National Natural Science Foundation of China, Multiphysics coupling in numerical reactor (11922505), 2020.01-2022.12

[1] Liu, Xiaojing*; Luo, Yuejian; Zhen, Cao; Guo, Rui; Cheng, Xu. Safety research of IVR-ERVC for advanced water cooled reactor. Energy, 156(1): 458-467, 2018.
[2] Liu, Xiaojing*; Ren, Shuo; Cheng, Xu. Development of a transverse mixing model for largescale impulsion phenomenon in tight lattice. Annals of Nuclear Energy, 101(0): 159~165, 2017.
[3] Liu X.J.*; Sun C.; Wang Z.D.; Chai X.; Xiong J.B.; Yang Y.H.; Cheng X. Preliminary study to improve the performance of SCWR-M during loss-of-flow accident. Nuclear Engineering and Design, 307(0): 431~444, 2016.
[4] Liu, X.J.*, Scarpelli, N. Development of a sub-channel code for liquid metal cooled fuel assembly. Annals of Nuclear Energy, 77:425~435, 2015.
[5] Liu, X.J.*; Cheng, X. Sub-channel/system coupled code development and its application to SCWR-FQT loop. Nuclear Engineering and Design, 285: 39~47, 2015.
[6] Ting Yang; Xiaojing Liu*; Xu Cheng. A circumferentially non-uniform fuel model and its application to thermal-hydraulic code. International Journal of Energy Research, 42(1): 188~197, 2018.
[7] Danhong Shen, Xiaojing Liu*, Xu Cheng. A new turbulent mixing modeling approach for sub-channel analysis code. Annals of Nuclear Energy, 121: 194~202, 2018.
[8] Luo Y.J.; Liu X.J.*, Cheng X. In- and ex-vessel coupled analysis for in-vessel retention. Progress in Nuclear Energy, 109: 74~82, 2018.
[9] Li shengzhe, Xiaojing Liu*. Development of boron tracking and boron hideout (CRUD) model based on subchannel approach. Nuclear Engineering and Design, 338:166-175, 2018.
[10] Xu, W; Xia, JH ;Liu, XJ*; Cheng, X; Zeng, W. Study of Bottom Reflooding in a Narrow Rectangular Channel. Nuclear Technology, 2018:1-16, 2018.
[11] Xu, Wei; Xia, Jianhua; Liu, Xiaojing*; Cheng, Xu; Zeng, Wei. Experimental investigation of bottom reflooding and modeling of quench velocity in a narrow rectangular channel. Progress in Nuclear Energy, 105:21-28, 2018.
[12] Li, Dong; Liu, Xiaojing*; Yang, Yanhua. Investigation of uncertainty quantification method for BE models using MCMC approach and application to assessment with FEBA data. Annals of Nuclear Energy, 107:62-70, 2017.
[13] Li, Dong; Liu, Xiaojing; Yang, Yanhua. Improvement of reflood model in RELAP5 code based on sensitivity analysis. Nuclear Engineering and Design, 303:163-172, 2016.
[14] Cheng X., Yang Y.H., Liu X.J. SCWR‐M: Design and Key technologies, Shanghai Jiao Tong University Press, 2015
[15] Liu X., Cheng X., Validation of the ATHLET-SC code by trans-critical transient dataKerntechnik, volume: 81, issue: 2, pages:164-166. Published: 2016
[16] Guo R., Xu W., Cao Z., Liu X. J., Cheng X. A new method to study the transient feasibility of IVR-ERVC strategy, Progress in Nuclear Energy, volume: 87, issue: pages:47-53. Published: 2016
[17] Cao Z., Liu X. J., Cheng X. A two dimensional approach for temperature distribution in reactor lower head during severe accident, Annals of Nuclear Energy, volume: 85, issue: pages:467-480. Published: 2015
[18] Jin Y., Xu W., Liu X. J., Cheng X., In- and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR, Annals of Nuclear Energy, volume: 80, issue: pages:322-337. Published: 2015
[19] Liu X. J., Cheng X. Sub-channel/system coupled code development and its application to SCWR-FQT loop, Nuclear Engineering and Design, volume: 285, issue: pages:39-47. Published: 2015
[20] Liu X. J., Scarpelli N., Development of a sub-channel code for liquid metal cooled fuel assembly Annals of Nuclear Energy, volume: 77, issue: pages:425-435. Published: 2015
[21] Yang T., Liu X. J., Cheng X., Investigation on heat transfer non-uniformity in rod bundle Nuclear Engineering and Design, volume: 265, issue: pages:222-231. Published: 2013
[22] Liu X. J., Schaefer A.Improvement of ATHLET modelling capability for asymmetric natural circulation phenomenon using uncertainty and sensitivity measures, Annals of Nuclear Energy, volume: 62, issue: pages:471-482. Published: 2013
[23] Liu X. J., Yang T., Cheng X. Development and assessment of a sub-channel code applicable for trans-critical transient of SCWR, Nuclear Engineering and Design, volume: 262, issue: pages:499-509. Published: 2013
[24] Liu X. J., Yang T., Cheng X., Thermal-hydraulic analysis of flow blockage in a supercritical water-cooled fuel bundle with sub-channel code, Annals of Nuclear Energy, volume: 59, issue: pages:194-203. Published: 2013
[25] Liu X. J., Yang T., Cheng X., Multi-layer fuel assembly design proposal for supercritical water cooled reactor, Progress in Nuclear Energy, volume: 67, issue: pages:82-87. Published: 2013
[26] Liu X. J., Fu S. W., Xu Z. H., Yang Y. H., Cheng X. LOCA analysis of SCWR-M with passive safety system, Nuclear Engineering and Design, volume: 259, issue: pages:187-197. Published: 2013
[27] Cheng X., Liu X. J., Hassan Y. , Topical issue on NUTHOS-8 Foreword,Nuclear Engineering and Design, volume: 249, issue: pages:1-1. Published: 2012
[28] Yang T., Liu X. J., Cheng X. Optimization of multilayer fuel assemblies for supercritical water-cooled reactors with mixed neutron spectrum, Nuclear Engineering and Design, volume: 249, issue: pages:159-165. Published: 2012
[29] Fu S. W., Liu X. J., Zhou C., Xu Z. H., Yang Y. H., Cheng X.Modification and application of the system analysis code ATHLET to trans-critical simulations, Annals of Nuclear Energy, volume: 44, issue: pages:40-49. Published: 2012
[30] Cheng X., Liu X. J., Gu H. Y.Fluid-to-fluid scaling of heat transfer in circular tubes cooled with supercritical fluids, Nuclear Engineering and Design, volume: 241, issue: 2, pages:498-508. Published: 2011
[31] Liu X. J., Yang T., Cheng X., Core and sub-channel analysis of SCWR with mixed spectrum core, Annals of Nuclear Energy, volume: 37, issue: 12, pages:1674-1682. Published: 2010
[32] Liu X. J., Kerner A., Schaefer A. , Using statistical sensitivities for adaptation of a best-estimate thermo-hydraulic simulation model, Nuclear Engineering and Design, volume: 240, issue: 10, pages:3413-3420. Published: 2010
[33] Liu X. J., Cheng X. , Coupled thermal-hydraulics and neutron-physics analysis of SCWR with mixed spectrum core, Progress in Nuclear Energy, volume: 52, issue: 7, pages:640-647. Published: 2010
[34] Liu X. J., Cheng X., CORE AND SUB-CHANNEL EVALUATION OF A THERMAL SCWR
[35] Nuclear Engineering and Technology, volume: 41, issue: 5, pages:677-690. Published: 2009
[36] Liu X. J., Cheng X., Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly, Annals of Nuclear Energy, volume: 36, issue: 1, pages:28-36. Published: 2009
[37] Gu H. Y., Yu Y. Q., Cheng X., Liu X. J.Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels, Nuclear Science and Techniques, volume: 19, issue: 3, pages:178-186. Published: 2008
[38] Cheng X., Liu X. J., Yang Y. H., A mixed core for supercritical water-cooled reactors, Nuclear Engineering and Technology, volume: 40, issue: 2, pages:117-126. Published: 2008

Nuclear Thermal Hydraulic undergraduate student 54

Guest Editor, Nuclear Engineering and Design
Editorial Advisory Board member, Nuclear Engineering and Design
Assistant Chair of TPC 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety
Over 45 times session chair in international meeting
Organizer of IAEA Course on Science and Technology of Supercritical water cooled reactors (SCWRs)
CNS&ANS member
[1] Assistant Chair of TPC: 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-8) October 10-14 2010, Shanghai, China.
[2] Director and local organizer: Joint SJTU-IAEA Course on Science and Technology of SCWRs, Shanghai, August 26-30, 2013.
[3] Track organizer: 10th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-10) Okinawa, JAPAN, 14-18 December, 2014
[4] Local organizer, 1st Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology, March 8-12, 2015, Shanghai, China
[5] Thermal Hydraulic Track Manager, 2016 International Youth Nuclear Congress (IYNC 2016), July 24th-30th, 2016, Hangzhou, China.
[6] Session review chair, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, IL Hyatt Regency Chicago, August 30-September 4, 2015.
[7] Special session organizer, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), Chicago, IL Hyatt Regency Chicago, August 30-September 4, 2015.
[8] Assistant TPC Chairs, Topical Meeting on Advances in Thermal Hydraulics-2016(ATH 16), New Orleans, LA Hyatt Regency New Orleans, June 12-16, 2016
[9] Invited speaker: Generation IV International Forum, San Diego, CA, USA, June 17 2010.
[10] Invited speaker: Generation IV International Forum, Shanghai, China, October 14, 2010.
[11] Invited lecturer: IAEA Course on Science and Technology of Supercritical Water Cooled Reactors, Italy Trieste, 2011.
[12] Invited lecturer: IAEA Course on Science and Technology of Supercritical Water Cooled Reactors, Shanghai China 2013.
[13] Invited speaker: 1st Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology, March 8-12, 2015, Shanghai, China
[14] TPC member: 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-8) October 10-14 2010, Shanghai, China.
[15] TPC member: 9th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-9) , September,9-13 2012,Kaohsiung,Taiwan.
[16] TPC member: 10th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-10) Okinawa, JAPAN, 14-18 December, 2014
[17] TPC member: The 7th Int. Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7) March 15-18, 2015, Hotel Radisson Blu Royal, Helsinki, Finland.
[18] Session Chair: Int. Workshop on Nuclear Safety and Severe Accidents (NUSSA)
[19] Session Chair: 8th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-8)
[20] Session Chair: 9th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-9) September,9-13 2012,Kaohsiung,Taiwan.
[21] Session Chair: 10th Int. Topical Meeting on Nuclear Thermal-Hydraulics Operation and Safety (NUTHOS-10) Okinawa, JAPAN, 14-18 December, 2014
[22] Session Chair: 19th Pacific Basin Nuclear Conference (PBNC-2014), 2014 August 24-28 Vancouver, Canada.
[23] Session Chair: The 7th Int. Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7) March 15-18, 2015, Hotel Radisson Blu Royal, Helsinki, Finland.
[24] Local organizer , 1st Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology 2015,
[25] Session review chair/ Special session organizer/session chair, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), August 30-September 4, 2015, Hyatt Regency Chicago
[26] Assistant TPC Chairs, Topical Meeting on Advances in Thermal Hydraulics-2016(ATH 16), 12–16 June 2016 New Orlean
[27] Track organizer/technical tour chair, 2016 International Youth Nuclear Congress (IYNC 2016), July 24-30, 2016 New Century Grand Hotel Hangzhou, Hangzhou, China

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.