Yang Liu
460 Turner Street, Suite 306, Blacksburg, VA 24061
Tel: 540.231.8068, Email: liu130@vt.edu
Present Position
Assistant Professor, Nuclear Engineering Program, Department of Mechanical Engineering,
Virginia Tech
Education
2008 Ph.D. in Nuclear Engineering, Purdue University, West Lafayette, IN
2003 M.S. in Nuclear Engineering, Shanghai Jiao Tong University, Shanghai, China
2000 B.S. in Nuclear Engineering, Shanghai Jiao Tong University, Shanghai, China
Area of Expertise
Nuclear thermal hydraulics and reactor safety
Two-phase flow modeling, instrumentation and experiment
Two-phase flow computational fluid dynamics
Advanced passive safety system design
Research Experience
08/2012 ~ Present, Assistant Professor
Nuclear Engineering Program, Department of Mechanical Engineering, Virginia Tech
• Development of a generic multi-field two-fluid model
• Design of an air-water two-phase flow loop for two-fluid model closure studies
• Flow visualization of interfacial structure development
• Simulation of bubble interactions using Volume of Fluid method
• CFD study on annular flow dynamics
12/2008 ~ 07/2012, Postdoctoral Research Associate
School of Nuclear Engineering, Purdue University
• Development of an advanced conductivity probe for droplet measurement
• Experimental study of two-phase flow in an 8x8 rod bundle
• Experiment and modeling of air entrainment on the suction side of ECCS pumps
• Experimental study on two-phase flow induced vibration on a pipe elbow
• Counter-current flow limitation experiment in a large diameter pipe
• Two-fluid model and interfacial area transport experiment under simulated microgravity
condition
08/2003 ~ 12/2008, Graduate Research Assistant
School of Nuclear Engineering, Purdue University
• Modeling of interfacial area transport in annular flows
• Experimental study of interfacial area transport with skewed inlet profiles
• Experimental study of churn-turbulent to annular flow transition
• Flow regime identification using an artificial neural network
• Modeling of drag force for the interfacial area transport equation development
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08/2000 ~ 06/2003, Graduate Research Assistant
School of Nuclear Engineering, Shanghai Jiao Tong University
• Study of heat transfer characteristics in a vertical narrow annulus
• Numerical simulation of a liquid metal magnetohydrodynamic system
Professional Affiliation
• American Nuclear Society, Member
• American Society of Mechanical Engineers, Member
Publication
Journal Papers in English
Lee, D.Y., Liu, Y., Hibiki, T., Ishii, M., Buchanan Jr, J.R., A study of adiabatic twophase flows using the two-group interfacial area transport equations with a modified twofluid model. International Journal of Multiphase Flow, Vol. 57, pp. 115-130. 2013.
Liu, Y., Lee, D.Y., Roy, T., Ishii, M., Buchanan Jr, J.R., The development of two-phase
flow structures in air–water planar bubble jets. International Journal of Multiphase Flow,
Vol. 56, pp. 25-39. 2013.
Liu, Y., Roy, T., Lee, D.Y., Ishii, M., Buchanan Jr, J.R., Experimental study of nonuniform inlet conditions and three-dimensional effects of vertical air–water two-phase flow
in a narrow rectangular duct. International Journal of Heat and Fluid Flow, Vol. 39, pp.
173-186. 2013.
Miwa, S., Liu, Y., Hibiki, T., Ishii, M., Kondoh, Y., Ukai, N., Tanimoto, K.,
Experimental study of counter-current gas–droplet flow limitation in a 30cm pipe. Chemical
Engineering Science, Vol. 92, pp. 167-179. 2013.
Yang, X., Schlegel, J.P., Liu, Y., Paranjape, S., Hibiki, T., Ishii, M., Experimental study
of interfacial area transport in air–water two phase flow in a scaled 8x8 BWR rod bundle.
International Journal of Multiphase Flow, Vol. 50, pp. 16-32. 2013.
Julia, J.E., Liu, Y., Hibiki, T., Ishii, M., Local flow regime analysis in vertical cocurrent downward two-phase flow. Experimental Thermal and Fluid Science, Vol. 44, pp.
345-355. 2013.
Chen, S.-W., Liu, Y., Hibiki, T., Ishii, M., Yoshida, Y., Kinoshita, I., Murase, M.,
Mishima, K., Experimental study of air–water two-phase flow in an 8 × 8 rod bundle under
pool condition for one-dimensional drift-flux analysis. International Journal of Heat and
Fluid Flow, Vol. 33, pp. 168-181. 2012.
Chen, S.-W., Liu, Y., Hibiki, T., Ishii, M., Yoshida, Y., Kinoshita, I., Murase, M.,
Mishima, K., One-dimensional drift-flux model for two-phase flow in pool rod bundle
systems. International Journal of Multiphase Flow, Vol. 40, pp. 166-177. 2012.
Liu, Y., Miwa, S., Hibiki, T., Ishii, M., Morita, H., Kondoh, Y., Tanimoto, K.,
Experimental study of internal two-phase flow induced fluctuating force on a 90° elbow.
Chemical Engineering Science, Vol. 76, pp. 173-187. 2012.
Yang, X., Schlegel, J.P., Liu, Y., Paranjape, S., Hibiki, T., Ishii, M., Measurement and
modeling of two-phase flow parameters in scaled 8x8 BWR rod bundle. International
Journal of Heat and Fluid Flow, Vol. 34, pp. 85-97. 2012.
Liu, Y., Hibiki, T., Sun, X., Ishii, M., Kelly, J.M., Drag coefficient in one-dimensional
two-group two-fluid model. International Journal of Heat and Fluid Flow, Vol. 29, pp.
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1402-1410. 2008.
Julia, J.E., Liu, Y., Paranjape, S., Ishii, M., Upward vertical two-phase flow local flow
regime identification using neural network techniques. Nuclear Engineering and Design,
Vol. 238, pp. 156-169. 2008.
Journal Papers in Chinese
Liu, Y., Shen, X., Chen, K., Liquid metal Magnetohydrodynamic power generation
system. Power Equipment, Vol. 5, pp. 45-48. 2002.
Shen, X., Liu, Y., Zhang, Q., Flow boiling heat transfer correlation for narrow channel.
Nuclear Power Engineering, Vol. 23, pp. 80-83. 2002.
Chen, K., Zhang, Q., Shen, X., Cai, R., Chen, P., Liu, Y., Zou, W., Real-time dynamic
CANDU 9 steam generator simulation. Boiler Technology, Vol. 32, pp. 1-6. 2001.
Shen, X., Chen, K., Liu, Y., Zhang, Q., A study on liquid lithium flow in rectangular
duct perpendicular to an intense magnetic field. Chinese Journal of Nuclear Science and
Engineering, Vol. 21, pp. 336-340. 2001.
Book Chapter
Liu, Y., Hibiki, T., Ishii, M., Modeling of interfacial area transport in two-phase flows,
in: Cheng, L., Mewes, D. (Eds.), Advances in multiphase flow and heat transfer, volume (4).
Bentham Sciences Publishers Ltd, pp. 3-27. 2012.
Conference Papers and Summaries
Williams, M., Liu, Y., Visual study of interfacial structures in a rectangular channel, to
appear in 2013 ANS Winter Meeting and Nuclear Technology Expo. Washington, DC,
November 10-14, 2013.
Liu, Y., Xiao, H., Numerical simulation of annular flow using volume of fluid method,
to appear in 2013 ANS Winter Meeting and Nuclear Technology Expo. Washington, DC,
November 10-14, 2013.
Brooks, C.S., Liu, Y., Hibiki, T., Ishii, M., Void fraction covariance in two-phase flows,
the 20th International Conference on Nuclear Engineering (ICONE20). July 30 – August 3,
Anaheim, California, 2012.
Mori, M., Sawant, P., Liu, Y., Ishii, M., Droplet deposition rate in vertical annular twophase flow, The 19th International Conference on Nuclear Engineering (ICONE-19). ChibaCity, Japan, May 16-19, 2011.
Roy, T., Liu, Y., Chen, S., Hibiki, T., Ishii, M., Duval, W., Experimental study of twophase flows under reduced gravity conditions, The 14th International Topical Meeting on
Nuclear Reactor Thermal Hydraulics (NURETH-14). Ontario, Canada, September 25-30,
2011.
Sawant, P., Liu, Y., Ishii, M., Mori, M., Chen, S., Droplet entrainment in gas-liquid
annular flow, The 14th International Topical Meeting on Nuclear Reactor Thermal
Hydraulics (NURETH-14). Ontario, Canada, September 25-30, 2011.
Yang, X., Schlegel, J.P., Paranjape, S., Liu, Y., Chen, S.W., Hibiki, T., Ishii, M.,
Interfacial area transport in two-phase flows in a scaled 8x8 rod bundle geometry at elevated
pressures, The 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
(NURETH-14). Toronto, Ontario, Canada, September 25-29, 2011.
Hibiki, T., Ishii, M., Liu, Y., Brooks, C., Overview of interfacial area transport equation
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development, 2010 American Nuclear Society Winter Meeting. Las Vegas, Nevada,
November 7–11, 2010.
Liu, Y., Ishii, M., Buchanan, J.R.J., Foundation of the interfacial area transport equation
in annular two-phase flows, International Conference on Multiphase Flow (ICMF 2010).
Proceedings. Tampa, Florida. USA, May 30-June 4, 2010.
Liu, Y., Hibiki, T., Ishii, M., Sun, X., Study of drag coefficient in bubbly flows, The
12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12).
Pittsburgh, PA, U.S.A., Sept. 30-Oct. 4, 2007.
Julia, J.E., Paranjape, S.S., Liu, Y., Ishii, M., Objective fast local flow regime
identification using conductivity probe and neural network techniques, The 11th
International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11).
Avignon, France, October 2-6, 2005.
Sun, X., Liu, Y., Ozar, B., Ishii, M., Kelly, J.M., Study on drag coefficients for two
groups of bubbles, The 12th International Conference on Nuclear Engineering (ICONE12).
Arlington, Virginia, USA, April 25–29, 2004.
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