Prashant Jain

Prashant K Jain

Interim Section Head, Advanced Reactor Engineering & Development, Nuclear Energy and Fuel Cycle Division

Contact

jainpk@ornl.gov | 865.574.6272

Bio

Dr. Prashant Jain is the interim Section Head for the Advanced Reactor Engineering and Development Section in the Nuclear Energy & Fuel Cycle Division at Oak Ridge National Laboratory. Prashant received his MS (2006) and Ph.D. (2010) in nuclear engineering from the University of Illinois, Urbana-Champaign, and his BTech (2004) in mechanical engineering from the Indian Institute of Technology, Bombay. He has over 15 years of experience in advanced multi-physics modeling, nuclear thermal design and safety analyses, computational fluid dynamics (CFD), single- and two-phase turbulent flows and heat transfer, analytical benchmarks, lattice Boltzmann method, and parallel scientific software development. At ORNL, he 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 served as an R&D analyst for the Spallation Neutron Source (SNS) Proton Power Upgrade project and its Second Target Station (STS) design project. He was also the principal developer of the ORNL’s lattice Boltzmann method CFD code, PRATHAM, and the thermo-fluidics thrust lead for the Transformational Challenge Reactor (TCR) project. He has also led multiple industry CRADAs (with Eaton Corporation, Gopher Resource, Alcoa USA, Linde Corporation, and Spar Energy) for the DOE’s High-performance Computing for Energy Innovation Program. Prashant is a recipient of the American Nuclear Society (ANS) Mark Mills Award for his doctoral research on lattice Boltzmann methods and UT-Battelle’s 2019 Mission Support Award for his contributions towards the HFIR event causal analysis.

Education

  • PhD, Nuclear Engineering, University of Illinois, Urbana-Champaign (2006-10)
  • MS, Nuclear Engineering, University of Illinois, Urbana-Champaign (2004-06)
  • BTech, Mechanical Engineering, Indian Institute of Technology, Bombay, India (2000-04)

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 90, C, C++, Python, Perl, and 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, and TecPlot.

Awards and Honors

  • Invited Panelist for the Government of India's VaiBhaV Summit (2020), which was a collaborative initiative by S&T and Academic Organizations of India, to bring out the comprehensive roadmap to leverage the expertise and knowledge of global Indian researcher for solving emerging challenges.
  • UT-Battelle Mission Support Award (2019) for distinguished performance and dedication in determining the causes of the first fuel element failure in 52 years of HFIR operation.
  • ORNL Significant Event Award (2012) for significant project accomplishments in developing Plutonium-238 production capabilities at the High Flux Isotope Reactor.
  • ORNL Significant Event Award (2011) for significant contributions to the support to DOE in response to nuclear crisis at Fukushima.
  • ORNL Appreciation Award (2011) for computational analysis activities related to the ORNL's response to the events at Fukushima Daiichi.
  • American Nuclear Society – Mark Mills Award (2010) for 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).

Proposals and Partnerships

Led successful research proposals for

  • DOE NNSA – Material Management and Minimization (M3) Program Office
  • DOE NE – NEAMS High-Impact Problem Research and NEUP Programs
  • DOE – Advanced Research Projects Agency (ARPA-E) Program
  • DOE – EERE High-Performance Computing for Manufacturing Program
  • U.S. Nuclear Regulatory Commission – Office of Nuclear Regulatory Research
  • ORNL – Seed Money Program
  • ORNL – Lab-directed Research and Development Program
  • NRC – Assessment of Digital Twins for Advanced Reactors

Industrial partnerships with

  • United Technologies Research Center (UTRC)            
  • Alcoa USA
  • Electric Power Research Institute (EPRI)                    
  • Wenesco LLC
  • Gas Technology Institute (GTI)                                  
  • First Solar
  • MetalTek International                                               
  • Gopher Resource
  • Eaton Corporation                                                      
  • Praxair, Inc
  • HolosGen LLC                                                            
  • X-energy
  • GE Renewable Energy (Hydro)                                   
  • Spar Energy

Academic and research collaborations with

  • Indian Institute of Technology, Bombay India
  • University of Illinois, Urbana-Champaign IL   
  • Kansas State University, Manhattan KS
  • University of Michigan, Ann Arbor MI
  • University of Tennessee, Knoxville TN
  • University of Missouri, Rolla MO
  • Virginia Commonwealth University, Richmond VA
  • Argonne National Laboratory, Lemont IL
  • Idaho National Laboratory, Idaho Falls ID

Publications - Book and Journal Articles

  1. D. J. Kropaczek, V. Badalassi, P.K. Jain, P. Ramuhalli, W.D. Pointer. Digital Twins for Nuclear Power Plants and Facilities. Book Chapter. To be submitted in: The Digital Twin Technology, Business Models, Operations and Applications, Springer (2022).
  2. J.M. Park, M. Cianciosa, K. Kim, E. Hassan, R. K. Archibald, R. W. Smith, M T. Kao, C. Daily, P.K. Jain. TokDesigner - A Theory-Based Design Tool for Fusion Reactors. To be submitted in: Nuclear Fusion (2022).
  3. J. Weinmeister, C. Jesse, P.K. Jain, B.J. Ade, D. Schappel. Coolant Channel Design for Additively Manufactured Reactor Cores. To be submitted in: Nuclear Science and Engineering (2022).
  4. A. Wysocki, P.K. Jain, S. Bhatt, and J. Rader. Transformational Challenge Reactor Accident Analyses. To be submitted in: Nuclear Science and Engineering (2022).
  5. N.S. Panicker, R. Chaudhary, V.M. Rao, M.O. Delchini, P.K. Jain. High-Fidelity Simulation Study of the Aluminum Smelting Process Using OpenFOAM. To be submitted in: Metallurgical and Materials Transactions B (2022).
  6. Brian J. Ade et al. Candidate Core Designs for the Transformational Challenge Reactor. Journal of Nuclear Engineering, 2, 74-85, 2021.
  7. V. Kumar, M. Harvey, M. Wendel, P.K. Jain, N.J. Evans. Thermal loading analysis of the ring injection dump for the Spallation Neutron Source facility. Nuclear Inst. and Methods in Physics Research, A, 1006 (2021) 165380.
  8. B.R. Betzler, B.J. Ade, A.J. Wysocki, P.K. Jain, P.C. Chesser, M.S. Greenwood, and K.A. Terrani. Transformational Challenge Reactor Pre conceptual Core Design Studies. Nuclear Engineering and Design, Vol. 367, 110781, 2020.
  9. M. Sandlin, K. Nawaz, B. Fricke, V.M. Rao, C. Cramer, E.L. Curzio, A. Elliott, and P.K. Jain. An Overview of the Design of High-Temperature Heat Exchangers: State of the Art Developments and Prospects. Submitted to Renewable and Sustainable Energy Reviews, 2020.
  10. 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.
  11. 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).
  12. 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).
  13. 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.
  14. 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.
  15. 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.
  16. 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.
  17. 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.
  18. 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.
  19. 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.
  20. 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.
  21. 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.

Publications - Technical Proceedings

  1. B.J. Ade et al. Transformational Challenge Reactor Design Characteristics. To be published in: International Conference on Physics of Reactors 2022 (PHYSOR 2022), Pittsburgh, PA, May 15–20, 2022.
  2. N.S. Panicker, R. Chaudhary, M.O. Delchini, V.M. Rao, P.K. Jain. Large Eddy Simulation study of Aluminum Smelting process using OpenFOAM. To be published in: 7th Thermal and Fluids Engineering Conference (Hybrid), Partially online virtual and in person at University of Nevada, Las Vegas, NV, USA May, 16-18, 2022.
  3. P.K. Jain, J. Weinmeister, B.J. Ade. CFD Modeling for the Transformational Challenge Reactor Preliminary Design. To be published in: International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Virtual Meeting, March 6–11, 2022.
  4. I. Jarrah, M.O. Delchini, V. Badalassi, P.K. Jain, J. Gounley. Implementation of the Energy Equation Solver to the Lattice Boltzmann Method-based Code PRATHAM. To be published in: International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Virtual Meeting, March 6–11, 2022.
  5. J. Weinmeister, A.S. Sabau, P.K. Jain. Additively Manufactured Surface Heat Transfer Enhancements for the Transformational Challenge Reactor. To be published in: International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Virtual Meeting, March 6–11, 2022.
  6. V.M. Rao, V. Kumar, A. Anderson, J. Grogan, P.K. Jain. Computational Methodology to Simulate Pyrometallurgical Processes in a Secondary Lead Furnace. To be published in: REWAS 2022 Symposia, TMS 2022 Annual Meeting & Exhibition, Anaheim, California, USA, February 27–March 3, 2022.
  7. B.J. Ade, P.K. Jain, J. Weinmeister, and B.R. Betzler. The Impact of Temperature Modeling Assumptions for the Transformational Challenge Reactor. In: Transactions of 2021 ANS Annual Meeting, June 13-16, 2021.
  8. P.K. Jain and N. See. Advanced CFD and Multiphysics Design Exploration at ORNL. Presentation at the: Siemens’ Digital Twin conference for the US Dept of Energy, April 21, 2021.
  9. D. Chandler, J. L. Meszaros, B. R. Betzler, J. W. Bae, D. H. Cook, V. D. Fudurich, T. Howard, C. J. Hurt, G. Ilas, P. K. Jain, and E. L. Popov. Fuel Conversion Efforts at the High Flux Isotope Reactor–a 2020 Status Update. In: Transactions of 2020 ANS Winter Meeting and Nuclear Technology Expo, November 2020.
  10. A. Wysocki, P.K. Jain, J. Rader. Transformational Challenge Reactor Accident Analysis. In: Transactions of 2020 ANS Winter Meeting and Nuclear Technology Expo, November 2020.
  11. J. Weinmeister, C. Jesse, P.K. Jain. Gas Coolant Channel Optimization for Transformational Challenge Reactor. In: Transactions of 2020 ANS Winter Meeting and Nuclear Technology Expo, November 2020.
  12. V.M. Rao, M. Delchini, P.K. Jain, and M.T. Ahmad. HPC to Enable Next-generation Low-temperature Waste Heat Recovery. Proceedings of the 2020 28th Conference on Nuclear Engineering, ICONE28-POWER2020, August 2-6, 2020, Anaheim, California, USA.
  13. J. Weinmeister, P.K. Jain. Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core. Research Summary. In: Transactions of American Nuclear Society Annual Meeting, June 2020.
  14. P.K. Jain. Challenges and Opportunities in Thermal Hydraulics of High-Temperature Gas-Cooled Reactors. Technical Panel Discussion. In: Transactions of American Nuclear Society Annual Meeting, June 2020.
  15. B. Betzler, B. Ade, A. Wysocki, P.K. Jain, S. Greenwood, J. Rader, J. Heineman, R. Kile, N. Brown, K. Terrani. Power Level Down-Selection for the Transformational Challenge Reactor. Research Summary. In: Transactions of American Nuclear Society Annual Meeting, June 2020.
  16. N.S. Panicker, M. Delchini, T. Sambor, A.S. Sabau, and P.K. Jain. Advanced Thermal-Hydraulic Model of Heat Recovery Steam Generators. 5thThermal and Fluids Engineering Conference (TFEC), May 26-28, 2020.
  17. P.K. Jain. Thermal-Hydraulics Modeling and Simulation Capabilities for Advanced Reactor Design and Safety Evaluations. Technical Presentation. In: 2019 Global Center for Nuclear Energy Partnership (GCNEP) Working Group Meeting, December 2019.
  18. P.K. Jain. An Overview of Research on Molten Salt Reactors. Technical Presentation. In: 2019 Global Center for Nuclear Energy Partnership (GCNEP) Working Group Meeting, December 2019.
  19. D. Chandler, B.R. Betzler, P.K. Jain, J.W. Bae, D.H. Cook, V.D. Fudurich, T.K. Howard, C.J. Hurt, G. Ilas, J.L. Meszaros, E. Popov. High Flux Isotope Reactor Conversion from High-Enriched to Low-Enriched Uranium Fuel – a 2019 Progress Update. Abstract and Presentation. In: Reduced Enrichment for Research and Test Reactors (RERTR) 2019 Meeting, Zagreb, Croatia, October 6-9, 2019.
  20. T.K. Howard, P.K. Jain, and E.L. Popov. Verification and Validation of COMSOL for Heat Transfer in Thin Rectangular Channels using NASA Test Results. Research article. In: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, Oregon, August 18-23, 2019. 
  21. P.K. Jain. Renewed Emphasis on Advanced Modeling, Simulation, and Testing for the LEU Silicide Fuel in Response to the Recent HFIR Event. Technical Presentation. In: U.S. High-Performance Research Reactors (USHPRR) 2019 Meeting, July 2019.
  22. P.K. Jain. High-Performance Computing to Enable Next-generation Low-temperature Waste Heat Recovery. ORNL CRADA NFE-18-07223. Technical Review Presentation for the U.S. DOE Advanced Manufacturing Office Program Review Meeting, Washington DC, June 11-12, 2019.
  23. V.M. Rao, M. Delchini, M.T. Kao, P.K. Jain, and S. Subramanian. HPC to Enable Next-generation Low-temperature Waste Heat Recovery. Technical Poster for the U.S. DOE Advanced Manufacturing Office Program Review Meeting, Washington DC, June 11-12, 2019.
  24. D. Renfro, B. Betzler, D. Chandler, D. Cook, V. Fudurich, C.J. Hurt, G. Ilas, P.K. Jain, E. Popov. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. Abstract and Presentation. In: Reduced Enrichment for Research and Test Reactors (RERTR) 2018 Meeting, Edinburgh, U.K., November 4-7, 2018.
  25. P.K. Jain. Improving Nuclear Safety Through Multiphysics Modeling and Simulations. Technical Poster. In: COMSOL Conference 2018, Boston, MA, October 3-5, 2018.
  26. 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.
  27. 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.
  28. 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.
  29. 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.
  30. D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: U.S. High-Performance Research Reactors (USHPRR) Working Group Meeting, Gaithersburg, MD, USA, July 2016.
  31. 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.
  32. 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.
  33. 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.
  34. 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.
  35. D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: U.S. High-Performance Research Reactors (USHPRR) Working Group Meeting, Argonne, IL, USA, June 2015.
  36. 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.
  37. D. Renfro et al. Continuing LEU Conversion Activities at the High Flux Isotope Reactor. In: U.S. High-Performance Research Reactors (USHPRR) Working Group Meeting, Richland, WA, USA, July 2014.
  38. 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.
  39. 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.
  40. 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.
  41. 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.
  42. 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.
  43. 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.
  44. 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.
  45. 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.
  46. 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.
  47. 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.
  48. 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.
  49. 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.
  50. 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.
  51. 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.
  52. 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.
  53. 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.
  54. 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.
  55. 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.
  56. 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.
  57. 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.
  58. 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.
  59. 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.
  60. 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.
  61. 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.

Publications - Technical Reports

  1. V. Yadav, V. Agarwal, A.V. Gribok, R.D. Hays, A.J. Pluth, C.S. Ritter, H. Zhang, P.K. Jain, P. Ramuhalli, D. Eskins, J. Carlson, R.L. Gascot, C. Ulmer, R. Iyengar. Technical Challenges and Gaps in Digital Twin Enabling Technologies for Nuclear Reactor Applications. TLR/RES-DE-REB-2021-17, INL/EXT-21-65316, December 2021.
  2. N.S. Panicker, R. Chaudhary, M.O. Delchini, V.M. Rao, P.K. Jain. Computational Fluid Dynamics Simulations to Support Efficiency Improvements in Aluminum Smelting Process. ORNL/TM-2021/2341, NFE-19-07798, December 2021.
  3. P.K. Jain, M.T. Kao, V.M. Rao, E. L. Popov, D.T. Nguyen, J. Wilson, V. Badalassi, W.D. Pointer. Computational Fluid Dynamics Modeling to Simulate a Combined Reforming Process for Syngas and Hydrogen Production. ORNL/TM-2021/2313, CRADA/NFE-20-08198, November 2021.
  4. J. Gounley, M.A. Dumas, M. Delchini, P.V. Lara, P.K. Jain, A. Sircar, A. Spannaus. Performant High-Order Lattice Boltzmann for Exascale Applications. FY21 LDRD Project Report, LOIS ID 9756, October 2021.
  5. J.M. Park, M. Cianciosa, K. Kim, E. Hassan, R.K. Archibald, R.W. Smith, M.T. Kao, C. Daily, P.K. Jain. A Theory-Based Design Tool for Fusion Reactors. FY21 LDRD Project Report, LOIS ID 9879, October 2021.
  6. R. Archibald, M. Cianciosa, C. Daily, L. Drane, E. Hassan, P.K. Jain, M.T. Kao, K. Kim, J. Lore, R. Smith, J.M. Park. Tokamak Reactor Engineering Environment Technical Report. ORNL/TM-166287, September 2021.
  7. V.M. Rao, V. Kumar, A. Anderson, P.K. Jain. High-Accuracy Simulations to Model Pyrometallurgical Processes in a Secondary Lead Reverberatory Furnace. ORNL/TM-2021/2129, CRADA/NFE-19-07865, August 2021.
  8. T.K. Howard, P.K. Jain. A Verification and Validation Approach for COMSOL Multiphysics to Support the High Flux Isotope Reactor (HFIR). ORNL/TM-2021/1885, July 2021.
  9. V. Yadav, H. Zhang, C.P. Chwasz, A.V. Gribok, C. Ritter, N.J. Lybeck, R.D. Hays, T.C. Trask, P.K. Jain, V. Badalassi, P. Ramuhalli, D. Eskins, R.L. Gascot, D. Ju, R. Iyengar. The State of Technology of Application of Digital Twin. TLR/RES-DE-REB-2021-01, INL/EXT-21-01124, June 2021.
  10. A. Wysocki, J. Rader, S. Bhatt, P.K. Jain. Transformational Challenge Reactor: Preliminary Safety Analyses. ORNL/TM-2020/1738, October 2020.
  11. B.R. Betzler et al. Transformational Challenge Reactor Conceptual Design Report. ORNL/SPR-2020/1433, February 2020.
  12. V.M. Rao, M.G. Delchini, M.T. Ahmad, P.K. Jain. High-Performance Computing to Enable Next-Generation Low-Temperature Waste Heat Recovery. ORNL/TM-2019/1455, December 2019.
  13. B.R. Betzler, B.J. Ade, A.J. Wysocki, M.S. Greenwood, J.J.W. Heineman, P.C. Chesser, P.K. Jain, F. Heidet, A. Bergeron. Advanced Manufacturing for Nuclear Core Design. ORNL/TM-2019/1258, August 2019.
  14. P.K. Jain. Independent Review of HFIR Fuel Plate Welding Failure Analysis. C-HFIR-2019-002, R1, August 2019.
  15. C. Carathers, et al. Oak Ridge National Laboratory HFIR OFE-488 Fuel Element Failure Causal Theory Evaluation Interim Report. ORNL/TM-2019/1120, February 2019.
  16. K. Nawaz, M. Sandlin, C. Cramer, A. Elliot, P. Jain, E. Lara-Curzio, and B. Fricke. Development of Next-Generation Heat Exchangers for Hybrid Power Generation. ORNL/SPR-2018/1063, October 2018.
  17. B.R. Betzler, B.J. Ade, A.J. Wysocki, M.S. Greenwood, K.G. Field, J.M. Risner, P.K. Jain, J.R. Burns, B.D. Hiscox, K.A. Terrani. Transformational Challenge Reactor Pre conceptual Design Incorporating Rapid Prototyping via Advanced Manufacturing. ORNL/SPR-2018/1008, September 2018.
  18. 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.
  19. 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.
  20. 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.
  21. 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.
  22. 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.
  23. 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.
  24. 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.
  25. 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.
  26. 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.
  27. 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.
  28. 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.
  29. 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.
  30. 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.
  31. 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.
  32. 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.
  33. P.K. Jain. Simulation of Two-Phase Dynamics using Lattice Boltzmann Method. Ph.D. Dissertation, the University of Illinois at Urbana Champaign, Urbana IL, USA, 2010.
  34. P.K. Jain. Numerical Analysis of Flow Stability in a Natural Circulation Loop with Supercritical Fluid. M.Sc. Dissertation, the University of Illinois at Urbana Champaign, Urbana IL, USA, 2006.

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