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Subash Sharma

headshot of Dr. Subash Sharma
Subash Sharma, Ph.D Assistant Professor

Expertise

Nuclear Reactor Safety and Thermal-Hydraulics; Computational Fluid Dynamics (CFD); Two-Phase Flow and Heat Transfer Modeling, Experiments, and Simulations

Research Interests

Fluid Mechanics, Heat and Mass Transfer, Boiling, Computational Fluid Dynamics (CFD), Gas-Liquid Two-Phase Flow Experiments and Simulations, Nuclear Reactors Thermal-Hydraulics, Two-Phase Flow System instabilities, Two-Fluid Model and Drift Flux Model for Two-Phase flow

Education

  • Ph D: Nuclear Engineering, (2016), Purdue University - West Lafayette, Indiana, USA
  • MS: Chemical Engineering, (2004), Indian Institute of Technology Bombay - Mumbai, India
  • BS: Chemical Engineering, (2002), University of Mumbai - India

Biosketch

August 2019 - Present: Assistant Professor, Department of Chemical Engineering, University of Massachusetts, Lowell, MA, USA
August 2016 - August 2019: Post-Doctoral Research Associate, School of Nuclear Engineering, Purdue University, West Lafayette, IN, USA
August 2009 - July 2016: Graduate Research Assistant and Bilsland Fellow (2014-2015), School of Nuclear Engineering, Purdue University, West Lafayette, IN, USA
August 2006 - August 2009: Scientific Officer-D (Executive Engineer), Thermal Hydraulics and LOCA Analysis section, Reactor Safety Analysis group, Nuclear Power Corporation of India Ltd., Mumbai, Maharashtra, India.
September 2004 - August 2006: Scientific Officer-C (Engineer), Thermal Hydraulics and LOCA Analysis section, Reactor Safety Analysis group, Nuclear Power Corporation of India Ltd., Mumbai, Maharashtra, India.
July 2002 - July 2004: DGFS Fellow (while doing Masters as a graduate student), Indian Institute of Technology (I.I.T.) Bombay, Mumbai, India.

Selected Awards and Honors

  • Bilsland Dissertation Fellowship (2014), Scholarship/Research - Purdue University
  • Outstanding Service Scholarship (2012), Service, Community - Purdue University
  • Department of Atomic Energy Graduate Fellowship (2002), Scholarship/Research - Bhabha Atomic Research Centre (BARC), (Gov. of India)

Selected Publications

  • Sharma, S., Buchanan, J.R., de Bertodano, M.A. (2020). Density Wave Instability Verification of CFD Two-Fluid Model. Nuclear Science and Engineering, 1-11.
  • Sharma, S.L., Ishii, M., Hibiki, T., Schlegel, J.P., Liu, Y., Buchanan Jr., J.R. (2019). Beyond Bubbly Two-Phase Flow Investigation using a CFD Three-Field Two-Fluid Model. International Journal of Multiphase Flow, 113 1-15.
  • Chetty, K., Appiah, R., Lopez-de-Bertodano, A., Sweeney, C., Sharma, S., Buchanan, J., Lopez-de-Bertodano, M. (2019). Density Wave Instability Verification of 1D Two-Fluid CFD Model. Transactions of the American Nuclear Society, 121(1) 1731-1734.
  • Sharma, S., Chetty, K., Lopez de Bertodano, A., Clausse, A., Lopez de Bertodano, M.A. (2019). Stability and Simulation of a Boiling Channel with Two-Fluid Model CFD- Task 1&2 Final Report. Purdue University Technical Report PU/NE-18-06, submitted to Bettis Atomic Power Laboratory.
  • Sharma, S., Foster, P., Lopez de Bertodano, M.A. (2017). Stability and Simulation of a Boiling Channel with Two-Fluid Model CFD. Purdue University Technical Report PU/NE-17-14, submitted to Bettis Atomic Power Laboratory.
  • Sharma, S., Chetty, K., Lopez de Bertodano, M.A. (2017). Two-Fluid Model for 3D Cap-Bubbly Flow Simulations. Purdue University Technical Report PU/NE-17-06, submitted to Bettis Atomic Power Laboratory.
  • Sharma, S., Hibiki, T., Ishii, M., Schlegel, J., Buchanan, J., Hogan, K., Guilbert, P. (2017). An interfacial shear term evaluation study for adiabatic dispersed air–water two-phase flow with the two-fluid model using CFD. Nuclear Engineering and Design, 312 389-398.
  • Ishii, M., Schlegel, J.P., Lin, Y.C., Sharma, S. (2016). Boiling IATE Model Development and Verification of ANSYS CFX Tools Packages, Task 3: Verification of the Non-Local Tools Package. Purdue University Technical Report PU/NE-16-09, submitted to Bettis Atomic Power Laboratory.
  • Ishii, M., Schlegel, J.P., Lin, Y.C., Sharma, S. (2016). Boiling IATE Model Development and Verification of ANSYS CFX Tools Packages, Task 4: Separate Effect Study of Lift, Near Wall Forces, and Interfacial Area in Boiling Flows. Purdue University Technical Report PU/NE-16-26, submitted to Bettis Atomic Power Laboratory.
  • Ishii, M., Schlegel, J.P., Lin, Y.C., Sharma, S. (2016). Boiling IATE Model Development and Verification of ANSYS CFX Tools Packages, Task 5: Verification of the Volumetric Boiling Package. Purdue University Technical Report PU/NE-16-27, submitted to Bettis Atomic Power Laboratory.
  • Ishii, M., Schlegel, J.P., Lin, Y.C., Sharma, S. (2016). Boiling IATE Model Development and Verification of ANSYS CFX Tools Packages, Task 6: Group-2 Boiling Suppression Strategy. Purdue University Technical Report PU/NE-16-28, submitted to Bettis Atomic Power Laboratory.
  • Chen, S., Macke, C., Hibiki, T., Ishii, M., Liu, Y., Ju, P., Sharma, S., Kondo, Y., Kawamizu, T., Yoshimoto, T., others, . (2016). Experimental Study of Horizontal Bubble Plume With Computational Fluid Dynamics Benchmarking. Journal of Fluids Engineering, 138(11).
  • Ishii, M., Schlegel, J.P., Lin, Y.C., Sharma, S. (2016). IATE Boiling Model Development and Verification of ANSYS CFX Tools Packages, Task 2: Revision of Group 1 Boiling Models. Purdue University Technical Report PU/NE-15-08, submitted to Bettis Atomic Power Laboratory.
  • Sharma, S. (2016). Investigation of Gas-Liquid Two-Phase Flow Using Three-Field Two-Fluid Model and Two-Group Interfacial Area Transport Equation in CFD Code. PhD Thesis, School of Nuclear Engineering, Purdue University.
  • Ishii, M., Schlegel, J.P., Zhu, Q., Yang, X., Sharma, S. (2016). Model Development for churn-turbulent to annular flows. Purdue University Technical Report PU/NE-16-10, submitted to Bettis Atomic Power Laboratory.
  • Rassame, S., Griffiths, M., Yang, J., Ju, P., Sharma, S., Hibiki, T., Ishii, M. (2015). Experimental investigation of void distribution in suppression pool over the duration of a loss of coolant accident using steam-water two-phase mixture. Annals of Nuclear Energy, 75 570-580.
  • Schlegel, J.P., Sharma, S., Cuenca, R., Hibiki, T., Ishii, M. (2014). Local flow structure beyond bubbly flow in large diameter channels. International journal of heat and fluid flow, 47 42--56.
  • Sharma, S., Schlegel, J.P., Ishii, M. (2014). Task 2.1: Interfacial Area measurement in Bubbly to Cap-Turbulent and Cap-Turbulent to Churn-Turbulent transition region. Purdue Technical Report PU/NE-14-06, submitted to Bettis Atomic Power Laboratory.
  • Ishii, M., Hibiki, T., Sharma, S., Schlegel, J.P., Zhao, Y. (2013). Implementation of interfacial area transport equation into 3-D CFD code, task 1: spatial benchmarking of interfacial area transport equation, subtask 1h: Diffusion Force Model Development and Near Wall Treatment of Two-Fluid Model. Purdue University Technical Report PU/NE-13-13, submitted to Bettis Atomic Power Laboratory.
  • Ishii, M., Hibiki, T., Liu, Y., Sharma, S., Lee, D.Y., Brooks, C. (2012). Implementation of interfacial area transport equation into 3-D CFD code, task 1: spatial benchmarking of interfacial area transport equation, subtask 1f: Systematic Benchmarking of the Two-group IATE with Two Gas Momentum Equations for Uniform and Non-Uniform Inlet Boundary Conditions. Purdue University Technical Report PU/NE-12-07, submitted to Bettis Atomic Power Laboratory.
  • Ishii, M., Hibiki, T., Liu, Y., Sharma, S. (2012). Implementation of interfacial area transport equation into 3-D CFD code, task 1: spatial benchmarking of interfacial area transport equation, subtask 1g: Additional Diffusion Force Model Development and Near Wall Treatment of Two-Fluid Model. Purdue University Technical Report PU/NE-12-20, submitted to Bettis Atomic Power Laboratory
  • Ishii, M., Hibiki, T., Liu, Y., Ju, P., Yang, X., Sharma, S., Miwa, S., Griffiths, M. (2012). Test Section Modification for Rod Bundle Void Fraction and Film Thickness Experiments. Purdue University Technical Report PU/NE-12-13, submitted to USNRC.
  • Ishii, M., Hibiki, T., Schlegel, J.P., Macke, C., Sharma, S., Cuenca, R.M. (2012). Void Fraction Data in Large Diameter Pipes: Generation of Interfacial Area Concentration Data. Purdue University Technical Report PU/NE-12-14, submitted to USNRC.
  • Ishii, M., Hibiki, T., Lee, D.Y., Sharma, S.L., Liu, Y. (2011). Implementation of interfacial area transport equation into 3-D CFD code, task 1: spatial benchmarking of interfacial area transport equation, subtask 1e: Preliminary Implementation of Two-Group Interfacial Area Transport Equation with Two Gas Momentum Equations and Testing with Uniform Inlet Conditions. Purdue University Technical Report PU/NE-11-09, submitted to Bettis Atomic Power Laboratory.
  • Sharma, S., Yang, X., Hibiki, T., Ishii, M. (2011). Assessment of interfacial drag and two phase pressure drop models of TRACE code. Proceedings of NURETH-14; 2011 September 25-30; Toronto; Canadian Nuclear Society; Paper no. 358
  • Ishii, M., Hibiki, T., Sharma, S. (2010). Task Order 2, Subtask 3: TRACE code Assessment for Air-Water Two Phase Flow in a Rod Bundle Geometry. Purdue University Technical Report , PU/NE-10-15, submitted to USNRC
  • Sharma, S., Kumar, K.P., Rammohan, H.P., Malhotra, P.K., Ghadge, S.G., Chandra, U. (2010). Three Miles Island-2 Accident Analysis using RELAP5/SCDAP code. 20th National and 9th International ISHMT-ASME Heat and Mass Transfer Conference,
  • Sharma, S., Dube, B.M., Pahari, S., Pramod, P., Rammohan, H.P., Malhotra, P.K., Ghadge, S.G. (2008). Plant Transient Analysis for TAPS-3&4 on Instrumented Relief Valves Stuck Open. International Conference on Reliability, Safety and Quality Engineering (ICRSQE),
  • Dube, B.M., Sharma, S., Pahari, S., Pramod, P., Rammohan, H.P., Malhotra, P.K., Ghadge, S.G. (2008). Plant Transient Analysis of Boiler Feed Pump Trip for KAPS 1&2. International Conference on Reliability, Safety and Quality Engineering (ICRSQE),
  • Sharma, S., Rammohan, H.P., Malhotra, P.K., Ghadge, S.G. (2008). Large break LOCA analysis for TAPS-3&4 using RELAP-5/MOD 3.2 (2: pp. 994-1000). Proceedings of International Conference on Advances in Nuclear Power Plants, ICAPP 2008,
  • Sharma, S., Banerjee, S., Rammohan, H.P., Bajaj, S.S. (2006). Postulated Initiating Events and their Effect on Fuel Behaviour for Water Reactors. Metal Materials and Processes, 18(1) 73-84.
  • Sharma, S., Banerjee, S., Rammohan, H.P., Malhotra, P.K., Ghadge, S.G., Bajaj, S.S. (2006). Plant transient analysis for TAPS-3&4 using RELAP-5/MOD 3.2 (pp. 1213-1219). Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants- ICAPP'06,
  • Sharma, S., Rao, V.G., Iyer, K.N. (2004). Effect of Non-Condensable Gases on Subcooled Flow Boiling through Horizontal Annulus Geometry. Chemical Engineering Congress, CHEMCON-2004,