Prashant K Jain

Prashant K Jain (Oak Ridge National Laboratory)

Prashant K Jain

Nuclear Thermal Hydraulics Engineer

Bio

Dr. Prashant Jain is an R&D staff member in the Thermal Hydraulics and Irradiation Engineering group of the Reactor and Nuclear Systems Division at the Oak Ridge National Laboratory (ORNL). He has over 10 years of experience in nuclear thermal safety analysis, computational fluid dynamics, single- and two-phase turbulent flows and heat transfer, advanced multi-physics models, analytical benchmarks, lattice Boltzmann method, and parallel scientific software development. He has led or contributed in over 100 technical publications, including national and international journals, conference proceedings, technical reports, posters and presentations. At ORNL, Dr. Jain leads the development of advanced three-dimensional multi-physics design and safety basis models for the present highly enriched uranium core and the proposed low-enriched uranium core designs of the High Flux Isotope Reactor (HFIR). He also serves as an independent safety reviewer for the Pu-238 production program, low-flow qualification efforts for the HFIR beam tubes, and numerous other material irradiation tests and experiments. Dr. Jain is a legal permanent resident of the United States, and a citizen of India.

Education

Ph.D. in Nuclear Engineering, University of Illinois, Urbana-Champaign (2006-10)

M.S. in Nuclear Engineering, University of Illinois, Urbana-Champaign (2004-06)

Bachelor of Technology in Mechanical Engineering, Indian Institute of Technology, Bombay, INDIA (2000-04)

Awards

ORNL Significant Event Award (2012)

Nuclear Science and Engineering Directorate at ORNL conferred this award to recognize significant project accomplishments in developing Plutonium-238 production capabilities at the High Flux Isotope Reactor.

COMSOL Best Paper Award (2012)

Paper on design and safety basis simulations for Pu-238 bare pellet irradiation was selected as the best paper for COMSOL's annual conference in Boston in 2012.

ORNL Significant Event Award (2011)

Reactor and Nuclear Systems Division at ORNL conferred this award in recognition of significant contributions to the support to DOE in response to nuclear crisis at Fukushima.

ORNL Appreciation Award (2011)

Reactor and Nuclear Systems Division at ORNL conferred this award to recognize and appreciate my substantial role in computational analysis activities related to the ORNL's response to the events at Fukushima Daiichi.

American Nuclear Society – Mark Mills Award (2010)

This is a national award given each year by the American Nuclear Society (ANS) to recognize a graduate student author who submits the best original technical paper contributing to the advancement of science and engineering related to the atomic nucleus.

Member of the Alpha Nu Sigma National Honor Society (2006)

Sargent and Lundy Fellowship (2005-06)

Merit-cum-means Scholarship (2000-04)

Projects

Technical Skills

  • Experienced nuclear safety professional with specific focus on advanced multi-physics software and technology for high-fidelity modeling and simulation of nuclear systems.
  • Expert in industry leading computational fluid dynamics technologies including COMSOL Multiphysics, STAR-CCM+ and ANSYS Workbench.
  • Expert in many programming and scripting languages, including Fortran 77, Fortran 90, C, C++, Python, Perl, MATLAB.
  • Expert in parallel programming paradigms, including Message Passing Interface – MPI, OpenMP, and knowledgeable in GPU-based code acceleration methods, CUDA and OpenCL on leadership computing facilities.
  • Experience with other engineering tools and packages, including RELAP5, ATHENA, Pro-ENGINEER, SpaceClaim, LS-DYNA, MATLAB, Mathematica, VisIt, ParaView, TecPlot.
  • Trained on methods for reviewing safety analysis reports for nuclear packaging and performing confirmatory analysis.

Ongoing Activities

  • Leads the development of advanced multi-physics modeling and simulation capabilities for the HFIR low-enriched uranium conversion project under the auspices of the DOE National Nuclear Security Administration Office of Material Management and Minimization.
  • Serves as an independent safety reviewer for the Plutonium-238 production program that is sponsored by the National Aeronautics and Space Administration.
  • Responsible for performing independent safety reviews for the low-flow qualification of HFIR beam tubes and numerous other material irradiation tests and experiments using advanced computational fluid dynamics simulations.
  • Supports proposal and program development activities for the ORNL seed money and laboratory-directed R&D programs, nuclear energy advanced modeling and simulation program, nuclear regulatory commission, advanced manufacturing office, nuclear energy university program, nuclear safety research and development program, and high-performance computing for manufacturing program.
  • Supports development of a high-temperature capable centrifugal pump technology for molten salt reactors through advanced computational fluid dynamics simulations. 

Past Activities

  • Led the development of an ORNL lattice Boltzmann method code, PRATHAM, Parallel Thermal Hydraulics using Advanced Mesoscopic Methods.
  • Led the development of a parallel Cartesian mesh generator code, CartGen++ for high-performance computing applications.
  • Supported DOE Fukushima accident analysis efforts using exploratory hydrogen explosion simulations through time-dependent, explicit finite element methods in LS-DYNA, and computational fluid dynamics simulations using COMSOL Multiphysics and STAR-CCM+.
  • Developed and published infinite-series exact analytical solutions for a variety of multi-layer heat conduction problems.
  • Coupled ATHENA (Advanced Thermal Hydraulic Energy Network Analyzer) code with the National Institute of Standards and Technology Reference Property Database to include cryogenic and other fluid properties.
  • Guest graduate appointment at Argonne Natioanl Laboratory to collaborate on the development of an advanced multiphase lattice Boltzmann code package.
  • Supported development of an advanced utility toolkit to enable multi-variable couplings between different neutronics and thermal-hydraulics code systems.
  • Developed a parallel two-phase dynamics simulation toolkit using the lattice Boltzmann method to improve fundamental understanding of nuclear boiling water reactor applications.
  • Developed a flow-stability analysis code to predict flow instabilities in a natural circulation loop with supercritical water and CO2 fluids. 

Publications

Journal Articles

  • ​D. Franken, D. Gould, P.K. Jain, H. Bindra. Numerical Study of Air Ingress Transition to Natural Circulation in a High Temperature Helium Loop. In Press, Annals of Nuclear Energy, Vol. 111, January 2018.
  • C.J. Hurt, J.D. Freels, P.K. Jain, G.I. Maldonado. Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for Pu-238 Production. In Press, ASME Journal of Nuclear Engineering and Radiation Science, 2017 (NERS-16-1069).
  • C.J. Hurt, J.D. Freels, P.K. Jain, G.I. Maldonado. Thermo-Mechanical Safety Analyses for Pu-238 Production Target at the HFIR. In Press, ASME Journal of Nuclear Engineering and Radiation Science, 2017 (NERS-16-1070).
  • S. Singh, P.K. Jain, Rizwan-uddin. Analytical Solution for Three-Dimensional, Unsteady Heat Conduction in a Multilayer Sphere. Journal of Heat Transfer, Paper 101301, Vol. 138, October 2016.
  • D. Wang, I.C. Gauld, G.L. Yoder, L.J. Ott, G.F. Flanagan, M.W. Francis, E.L. Popov, J.J. Carbajo, P.K. Jain, J.C. Wagner, J.C. Gehin. Study of Fukushima Daiichi Nuclear Power Station Unit-4 Spent Fuel Pool. Nuclear Technology, 180(2):205-215, 2012.
  • S. Singh, P.K. Jain, Rizwan-uddin. Finite Integral Transform Method to Solve Asymmetric Heat Conduction in a Multilayer Annulus with Time-Dependent Boundary Conditions. Nuclear Engineering and Design, 83(2):144-154, 2011.
  • P.K. Jain, S. Singh, Rizwan-uddin. An Exact Analytical Solution for Two-Dimensional, Unsteady, Multilayer Heat Conduction in Spherical Coordinates. International Journal of Heat and Mass Transfer, 53(9-10):2133-2142, 2010.
  • P.K. Jain, A. Tentner, Rizwan-uddin. A Lattice Boltzmann Framework to Simulate Boiling Water Reactor Core Hydrodynamics. Computers and Mathematics with Applications, 58(5):975-986, 2009.
  • P.K. Jain, S. Singh, Rizwan-uddin. Analytical Solution to Transient Asymmetric Heat Conduction in a Multilayer Annulus. Journal of Heat Transfer, 131(1):011304(1-7), 2009.
  • S. Singh, P.K. Jain, Rizwan-uddin. Analytical Solution to Transient Heat Conduction in Polar Coordinates with Multiple Layers in Radial Direction. International Journal of Thermal Sciences, 47(3):261-273, 2008.
  • P.K. Jain, Rizwan-uddin. Numerical Analysis of Supercritical Flow Instabilities in a Natural Circulation Loop. Nuclear Engineering and Design, 238(8):1947-1957, 2008.
  • P.K. Jain, Y. Gu, Rizwan-uddin. Broadcasting Engineering Laboratories, Audio/Video and Data, in Real Time over the Internet. Advances in Engineering Education, 1(2):1-17, 2008

Refereed Proceedings

  • D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: Transactions of Reduced Enrichment for Research and Test Reactors (RERTR 2017) Meeting, Chicago, IL, USA, November 12-16, 2017.
  • P.K. Jain, J.D. Freels, D.H. Cook, E.L. Popov and D.G. Renfro. Advanced Multiphysics Computational Fluid Dynamics Models for the High Flux Isotope Reactor. In: Proceedings of RRFM-2017 (European Research Reactor Conference), Rotterdam, Netherlands, 14-18 May 2017.
  • J.J. Carbajo and P.K. Jain. Comparison of HFIR Core Hydraulic Models with Operational Data. In: Transactions of ANS Winter Meeting, Las Vegas, NV, November 6-10, 2016.
  • D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: Transactions of Reduced Enrichment for Research and Test Reactors (RERTR 2016) Meeting, Antwerp, Belgium, October 23-26, 2016.
  • D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: US High Performance Research Reactors (USHPRR) Working Group Meeting, Gaithersburg, MD, USA, July 2016.
  • P.K. Jain and J.D. Freels. Advanced Multiphysics Thermal Hydraulic Models for the High Flux Isotope Reactor. In: Transactions of the COMSOL 2015 Conference, Boston, MA, USA, October 2015.
  • D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: Transactions of Reduced Enrichment for Research and Test Reactors (RERTR 2015) Meeting, Seoul, South Korea, October 2015.
  • P.K. Jain and J.D. Freels. Advanced Multiphysics Thermal Hydraulic Models for the High Flux Isotope Reactor. In: Nuclear Reactor Thermal Hydraulics (NURETH-16) Conference, Chicago, September 2015.
  • P.K. Jain. Learn from COMSOL Multiphysics: 25 must have User-Centric features for any engineering analysis software. ORNL RNSD M&S Forum, July 2015.
  • D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: US High Performance Research Reactors (USHPRR) Working Group Meeting, Argonne, IL, USA, June 2015
  • D. Pointer, J.J. Carbajo, D. Felde, P.K. Jain, J. March-Leuba, E.L. Popov, K. Robb, R. Salko and G.L. Yoder. Reactor and Nuclear System Thermal-Hydraulics. Poster Presentation at: the NSED Advisory Committee Review meeting at ORNL, April 2015.
  • P.K. Jain and J.D. Freels. 3D Multi-Physics Analyses to Support Low Enriched Uranium (LEU) Conversion of HFIR. In: Transactions of the 2014 COMSOL Conference in Boston, MA USA, October 2014.
  • D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: US High Performance Research Reactors (USHPRR) Working Group Meeting, Richland, WA, USA, July 2014.
  • V.B. Khane, P.K. Jain. Steady State COMSOL Thermal-Hydraulics Models for ORNL’s High Flux Isotope Reactor. In: 2013 ANS Winter Meeting and Nuclear Technology Expo, Washington DC, November 10-14, 2013.
  • J.D. Freels, P.K. Jain, C.J. Hurt. Investigation of Thermal Contact Gas Gap Conductance using COMSOL Version 4.3b. In: 2013 COMSOL Conference, Boston, MA, October 9-11, 2013.
  • D. Wang, P.K. Jain, J.D. Freels. Application of COMSOL Pipe Flow Module to Develop a High Flux Isotope Reactor (HFIR) System Loop Model. In: 2013 COMSOL Conference, Boston, MA, October 9-11, 2013.
  • A.S. Joshi, P.K. Jain, J.A. Mudrich, E.L. Popov. PRATHAM: Parallel Thermal Hydraulics Simulations using Advanced Mesoscopic Methods. In: 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, CA, November 11-15, 2012.
  • J.N. Cantrell, E.J. Inclan, A.S. Joshi, E.L. Popov, P.K. Jain. CartGen++: Extending a CAD-Based Cartesian Mesh Generator for the Lattice Boltzmann Method. In: 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, CA, November 11-15, 2012.
  • V.B. Khane, P.K. Jain, J.D. Freels. Development of CFD Models to Support LEU Conversion of ORNL's High Flux Isotope Reactor. In: 2012 ANS Winter Meeting and Nuclear Technology Expo, San Diego, CA, November 11-15, 2012.
  • V.B. Khane, P.K. Jain, J.D. Freels. COMSOL Simulations for Steady State Thermal Hydraulics Analyses of ORNL's High Flux Isotope Reactor. In: COMSOL Conference, Newton, Mass, October 3-5, 2012.
  • J.D. Freels, P.K. Jain, R.W. Hobbs. Design and Nuclear Safety Related Simulations of Bare-Pellet Test Irradiations for the Production of Pu-238 in the High Flux Isotope Reactor using COMSOL. In: COMSOL Conference, Newton, Mass, October 3-5, 2012.
  • J.D. Freels, P.K. Jain. Multiphysics Simulations in the Complex 3D Geometry of the High Flux Isotope Reactor Fuel Elements Using COMSOL. In: COMSOL Conference, Newton, Mass, October 13-15, 2011.
  • P.K. Jain, J.D. Freels, D.H. Cook. COMSOL-based Multiphysics Simulations to Support HFIR's Conversion to LEU Fuel. In: Trans. Amer. Nucl. Soc., 104:1064-1066, 2011.
  • P.K. Jain, Rizwan-uddin. Artificial Interface Lattice Boltzmann (AILB) Model for Simulation of Two-Phase Dynamics (invited).  In: Proceedings of 2010 American Nuclear Society (ANS) Winter Meeting, Las Vegas NV, USA, November 7-11, 2010.
  • P.K. Jain, E.L. Popov, G.L. Yoder, Rizwan-uddin. Parallel Simulation of 2D/3D Flows using Lattice Boltzmann Models (LBM).  In:  Proceedings of 2010 American Nuclear Society (ANS) Winter Meeting, Las Vegas NV, USA, November 7-11, 2010.
  • P.K. Jain, Rizwan-uddin. Advances in Lattice Boltzmann Modeling (LBM) to Simulate Two-Phase Dynamics. In:  Proceedings of the 1st International Nuclear & Renewable Energy Conference (INREC-10), Amman, Jordan, March 21-24, 2010.
  • S. Singh, P.K. Jain, Rizwan-uddin.  Analytical Solution of Time-Dependent Multilayer Heat Conduction Problems for Nuclear Applications.  In:  Proceedings of the 1st International Nuclear & Renewable Energy Conference (INREC-10), Amman, Jordan, March 21-24, 2010.
  • P.K. Jain, A. Tentner, Rizwan-uddin. LBM Simulation of Liquid Drop Coalescence driven by Surface Tension. In: Proceedings of 2009 American Nuclear Society (ANS) Winter Meeting, Washington DC, USA, November 15-19, 2009.
  • P.K. Jain, A. Tentner, Rizwan-uddin. A Lattice Boltzmann Framework for the Simulation of Boiling Hydrodynamics in BWRs. In: Proceedings of 2008 American Nuclear Society (ANS) Annual Meeting, Anaheim CA, USA, June 8-12, 2008.
  • P.K. Jain, Rizwan-uddin.  A 3D, Parallel LBM to Simulate Gravity driven Bubbly and Slug Flows. In: Proceedings of 2007 American Nuclear Society (ANS) Winter Meeting, Washington DC, USA, November 11-15, 2007.
  • P.K. Jain, Rizwan-uddin.  Lattice Boltzmann Method (LBM) for Nuclear Engineering Applications. In: Proceedings of 2007 American Nuclear Society (ANS) Annual Meeting, Boston MA, USA, June 24-28, 2007.
  • P.K. Jain, S. Markidis, B.G. Jones, Rizwan-uddin, J.R. White, L.M.  Bobek.  Web-casting of Nuclear Reactor Experiments. In: Proceedings of American Nuclear Society (ANS) Winter Meeting, Albuquerque NM, USA, November 12-16, 2006.
  • K.D. Kim, P.K. Jain, Rizwan-uddin. Web- and System-code based, Interactive, Nuclear Power Plant Simulators.  In:  Proceedings of 5th International Topical Meeting on Nuclear Plant Instrumentation Controls, and Human Machine Interface Technology (NPIC & HMIT  2006), Albuquerque NM, USA, November 12-16, 2006.
  • P.K. Jain, J.F. Stubbins, Rizwan-uddin. Interactive Virtual Laboratory for Distance Education in Nuclear Engineering. In: Proceedings of PHYSOR-2006, American Nuclear Society’s Topical Meeting on Reactor Physics, Vancouver BC, Canada, September 10-14, 2006.
  • P.K.  Jain, Rizwan-uddin.   Steady State and Dynamic Analyses of Supercritical CO2 Natural Circulation Loop. In: Proceedings of ICONE-14, 14th International Conference on Nuclear Engineering, Paper 89103, Miami FL, USA, July 17-20, 2006.
  • P.K. Jain, Y. Gu, J.F. Stubbins, Rizwan-uddin. Broadcasting Nuclear Engineering Laboratories – Video and Data – in Real-Time over the Internet. In: Proceedings of American Society of Engineering Education (ASEE) Annual Conference, Chicago IL, USA, June 18-21, 2006.
  • E. Edwards, A. Sweet, M. Blanchard, R. Agasie, P.K. Jain, Rizwan-uddin.  Distance Reactor Laboratory and Virtual Tours.   In:  Proceedings of 2006 American Nuclear Society (ANS) Annual Meeting, Reno NV, USA, June 4-8, 2006.
  • P.K. Jain. LabVIEW-based, Interactive Virtual Laboratory for Nuclear Engineering Education. In: Proceedings of 2006 American Nuclear Society (ANS) Student Conference, Troy NY, USA, March 30- April 1, 2006.
  • P.K.  Jain.   Development of a Real-Time Web-Casting Interface for System Codes. In: Proceedings of 2006 American Nuclear Society (ANS) Student Conference, Troy NY, USA, March 30–April 1, 2006.

Technical Reports

  • D. Chandler, B. Betzler, D. Cook, G. Ilas, P.K. Jain, and D. Renfro. Feasibility Studies for High Flux Isotope Reactor Conversion to Low-Enriched Uranium U3Si2 Fuel. In Press, ORNL TM Report, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2017.
  • P.K. Jain. Independent Review of C-HFIR-2017-023 titled Design and Analysis of an Irradiation Target Capsule for the Production of Pu-238 using NpO2 pellets. August 2017.
  • P.K. Jain. Independent Review of C-HFIR-2016-041 titled Safety Basis Temperature and Expansion Calculation for Low Heat Flux SiC Cladding Rabbit Capsules. March 2017.
  • R.J. Belles, P.K. Jain, J.J. Powers. Oak Ridge National Laboratory Support of Non-Light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-Light Water Reactors. ORNL/TM-2017/117, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 2017.
  • C.J. Hurt, J.D. Freels, R.W. Hobbs, P.K. Jain, G.I. Maldonado. Thermal Safety Analyses for the Production of Plutonium-238 at the High Flux Isotope Reactor. ORNL/TM-2016/234, Oak Ridge National Laboratory, Oak Ridge, Tenn., July 2016.
  • K.R. Robb, P.K. Jain, T.J. Hazelwood. High-Temperature Salt Pump Review and Guidelines – Phase I Report. ORNL/TM-2016/199, Oak Ridge National Laboratory, Oak Ridge, Tenn., May 2016.
  • P.K. Jain. Independent Review of C-HFIR-2015-033 Rev.0 - Thermo-Mechanical Safety Analysis of a Pu-238 Fully Loaded Target Assembly for up to Three Irradiation Cycles in HFIR using COMSOL Multiphysics v5.1. July 2016.
  • P.K. Jain. Independent Review of C-HFIR-2015-041 - Extension and Improvements to the Steady-State Thermal Qualification of the HFIR HB-1 Beam Tube. June 2016.
  • P.K. Jain. Independent Review of C-HFIR-2015-019 - Temperature Verification and Expansion Calculation for SiC Cladding Specimens in a Rabbit Housing. September 2015.
  • P.K. Jain. Independent Review of C-HFIR-2013-029 Rev.4 - COMSOL Thermal-Structure Interaction Simulations of NpO2 Fully-Loaded Targets in HFIR. July 2014.
  • D.G. Renfro, D. Chandler, D. Cook, G. Ilas, P.K. Jain and J. Valentine. Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel. ORNL/TM-2014/154, Oak Ridge National Laboratory, Oak Ridge, Tenn., October 2014.
  • P.K. Jain. Independent Review of C-HFIR-2013-029 Rev.2 - COMSOL Thermal-Structure Interaction Simulations of NpO2 Fully-Loaded Targets in HFIR. February 2014.
  • D. Chandler, D.H. Cook, G. Ilas, P.K. Jain, D.G. Renfro. Conceptual Design Parameters for HFIR LEU U-Mo Fuel Conversion Experimental Irradiations. ORNL/LTR-2013/132, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2013.
  • P.K. Jain, J.D. Freels, D.H. Cook. 3D COMSOL Simulations for Thermal Deflection of HFIR Fuel Plate in the “Cheverton-Kelley” Experiments. ORNL/TM-2012/138, Oak Ridge National Laboratory, Oak Ridge, Tenn., August 2012.
  • J.D. Freels, I.T. Bodey, R.V. Arimilli, F.G. Curtis, K. Ekici, and P.K. Jain. Preliminary Multiphysics Analyses of HFIR LEU Fuel Conversion using COMSOL, ORNL/TM-2011/7, Oak Ridge National Laboratory, Oak Ridge, Tenn., June 2011.
  • P.K. Jain. Simulation of Two Phase Dynamics using Lattice Boltzmann Method. Ph.D. Dissertation, University of Illinois at Urbana Champaign, Urbana IL, USA, 2010.
  • P.K. Jain. Numerical Analysis of Flow Stability in a Natural Circulation Loop with Supercritical Fluid.  M.Sc. Dissertation, University of Illinois at Urbana Champaign, Urbana IL, USA, 2006.
  • P.K. Jain. Heat Removal Mechanisms in a Pressurized Heavy Water Reactor (PHWR) during Off-Normal Conditions. B.Tech.  Dissertation, Indian Institute of Technology (IIT) Bombay, Mumbai, INDIA, 2004.

Facilities Used

  • High Flux Isotope Reactor
  • Oak Ridge Leadership Computing Facility
  • EVEREST Visualization Facility
  • Consortium for Advanced Simulation of Light Water Reactors

Contact Information