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Mechanical Engineering


Xu Cheng

Adjunct Professor

Xu Cheng E-mail: xu.cheng@kit.edu

Prof. Cheng has over 25 years research experience and about 10 years teaching experience. Currently he is professor at Karlsruhe Institute of Technology (KIT) in Germany and at Shanghai Jiao Tong University (SJTU) in China, and Director of the Division of Innovative Nuclear Systems at KIT. He has supervised or is supervising more than 20 PhD students in both KIT and SJTU and gives 4 lectures for both undergraduate and Master students. He has published over 100 papers. His main research fields are nuclear thermal-hydraulics and nuclear safety.


Education

  • Ph.D., Mechanical Engineering, Technical University Braunschweig, Germany, 1991
  • Dipl.-Ing., Mechanical Engineering, Technical University Braunschweig, Germany, 1986
  • B.S., Nuclear Engineering, Xi’an Jiao Tong University, China, 1982

Positions

  • 2009 – present: Professor of Karlsruhe Institute of Technology (KIT), Director of Division of Innovative Nuclear Systems
  • 2009 – present: Chair Professor of Shanghai Jiao Tong University (SJTU)
  • 2006 - 2008: Professor, Dean, School of Nuclear Science and Engineering, Shanghai Jiao Tong University (SJTU)
  • 2002 – 2005: Head of the group Accelerator Driven Nuclear Systems (ADS) at the Institute for Nuclear and Energy Technologies of the Research Center Karlsruhe (FZK)
  • 2001 – 2002: Visiting scholar at Argonne National Laboratory (ANL) as a German representative participating in the US-DOE project: Advanced Accelerator Application (AAA)
  • 1997 - 2005: Scientific staff member at the Institute for Nuclear and Energy Technologies of the Research Center Karlsruhe (FZK)
  • 1994 - 1996: Scientific assistant at the Institute for Flow Mechanics and Flow Machinery of the Karlsruhe University
  • 1992 - 1993: Post-doctoral at the Institute of Technical Physics of the Research Center Karlsruhe (FZK), Germany

Main funded projects as coordinator

  • EC FP7 Project “Thermal-hydraulics of Innovative Nuclear Systems (THINS)”, 2010 – 2014
  • EU-China Collaboration Project “Supercritical Water In-Pile Fuel Qualification Test”, 2011 – 2014
  • Chinese National Key Fundamental Research (973) Project “Basic research on supercritical water cooled reactors”, 2007 – 2011
  • EC FP4 Project 'Data Base of Containment Thermal-Hydraulics (DABASCO)', 1997-2000

Main Publications

  • 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, 241(2), February 2011, 498-508
  • Cheng, X., Yang, Y.H., Huang, S.F., "A simplified method for heat transfer prediction of supercritical fluids in circular tubes", Annals of Nuclear Energy, 2009, V36 (8), 1120-1128.
  • Cheng, X., Yu, Y.Q., "Local thermal–hydraulic behavior in tight 7-rod bundles", Nuclear Engineering and Design, 2009, V239, 1944-1955
  • Cheng, X., Liu, X.J., Yang, Y.H., "A Mixed Core for Supercritical Water-Cooled Reactors", Nuclear Engineering and Technology, Vol. 40, No.1, February 2008, pp.1-10
  • Cheng, X., Yang, Y.H., "A Point-Hydraulics Model for Flow Stability Analysis", Nuclear Design and Engineering 238 (2008)", January 2008, 188-199
  • Cheng, X., Kuang, B., Yang, Y.H., "Numerical analysis of heat transfer in supercritical water cooled flow channels", Nuclear Engineering and Design, 2007, vol.237(3): 240-252
  • Cheng, X., Batta, A., Tak, N.I., "Investigation on turbulent heat transfer to lead–bismuth eutectic flows in circular tubes for nuclear applications", Nuclear Engineering and Design, vol. 236, no. 4, pp. 385–393, 2006
  • Cheng, X., "Experimental Studies on Critical Heat Flux in Vertical Tight 37-Rod Bundles Using Freon-12", International Journal of Multiphase Flow, vol. 31, no. 10-11, pp. 1198–1219, 2005
  • Cheng, X., Cahalan, J.E., Finck, P.J., "Safety Analysis of an Accelerator-Driven Test Facility", Nuclear Engineering and Design, Vol.229 (2004), pp.289-2306
  • Cheng, X., Schulenberg, T., Bittermann, D., Rau, P., "Design Analysis of Core Assemblies for Supercritical Pressure Conditions", Nuclear Engineering and Design, Vol.223, Issue 3, pp.279-294, August 2003

Memberships

  • Member of Executive Committee of Thermal-Hydraulics Division (THD) of American Nuclear Society (ANS), since 2012
  • Editorial advisory panel member of ICE publishing, ICE Proceedings in Energy, ISSN: 1751-4223, E-ISSN: 1751-4231 (since 2012).
  • Editor of journal “Nuclear Engineering and Design“, Elsevier Publisher, ISSN 0029-5493 (since 2011)
  • Member of editorial board of the Journal “Science and Technology of Nuclear Installations“, Hindawi Publishing Corporation (since 2008)
  • Section editors of Journal “Frontiers in Energy”, ISSN: 2095-1701, Springer publisher, (since 2007)
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