| Analytical solution to transient heat conduction in polar coordinates with multiple layers in radial direction S Singh, PK Jain International journal of thermal Sciences 47 (3), 261-273, 2008 | 168 | 2008 |
| Numerical analysis of supercritical flow instabilities in a natural circulation loop PK Jain Nuclear Engineering and Design 238 (8), 1947-1957, 2008 | 133 | 2008 |
| Analytical solution to transient asymmetric heat conduction in a multilayer annulus PK Jain, S Singh | 105 | 2009 |
| Finite integral transform method to solve asymmetric heat conduction in a multilayer annulus with time-dependent boundary conditions S Singh, PK Jain Nuclear Engineering and Design 241 (1), 144-154, 2011 | 85 | 2011 |
| An exact analytical solution for two-dimensional, unsteady, multilayer heat conduction in spherical coordinates PK Jain, S Singh International Journal of Heat and Mass Transfer 53 (9-10), 2133-2142, 2010 | 85 | 2010 |
| Study of Fukushima Daiichi nuclear power station unit 4 spent-fuel pool D Wang, IC Gauld, GL Yoder, LJ Ott, GF Flanagan, MW Francis, EL Popov, ... Nuclear technology 180 (2), 205-215, 2012 | 75 | 2012 |
| Analytical solution for three-dimensional, unsteady heat conduction in a multilayer sphere S Singh, PK Jain Journal of Heat Transfer 138 (10), 101301, 2016 | 30 | 2016 |
| A lattice Boltzmann framework to simulate boiling water reactor core hydrodynamics PK Jain, A Tentner Computers & Mathematics with Applications 58 (5), 975-986, 2009 | 30 | 2009 |
| Preliminary Evaluation of Alternate Designs for HFIR Low-Enriched Uranium Fuel D Renfro, D Chandler, D Cook, G Ilas, P Jain, J Valentine Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2014 | 24 | 2014 |
| Numerical study of air ingress transition to natural circulation in a high temperature helium loop D Franken, D Gould, PK Jain, H Bindra Annals of Nuclear Energy 111, 371-378, 2018 | 16 | 2018 |
| Analytical solution of time-dependent multilayer heat conduction problems for nuclear applications S Singh, PK Jain 2010 1st International Nuclear & Renewable Energy Conference (INREC), 1-6, 2010 | 13 | 2010 |
| High-Temperature Salt Pump Review and Guidelines—Phase I Report KR Robb, PK Jain, TJ Hazelwood US Department of Energy (DOE) SciTech Connect, 2016 | 11 | 2016 |
| High-Temperature Salt Pump Review and Guidelines—Phase I Report KR Robb, PK Jain, TJ Hazelwood US Department of Energy (DOE) SciTech Connect, 2016 | 11 | 2016 |
| Multiphysics Simulations of the Complex 3D Geometry of the High Flux Isotope Reactor Fuel Elements Using COMSOL JD Freels, PK Jain COMSOL Conference, Boston, 2011 | 11 | 2011 |
| Preliminary multiphysics analyses of HFIR LEU fuel conversion using COMSOL JD Freels, IT Bodey, RV Arimilli, FG Curtis, K Ekici, PK Jain ORNL/TM-2011/07, Oak Ridge National Laboratory, 2011 | 11 | 2011 |
| Web-casting of nuclear reactor experiments P Jain, S Markidis, BG Jones, JR White, LM Bobek Transactions of the American Nuclear Society 95, 994-996, 2006 | 8 | 2006 |
| Thermal Safety Analyses for the Production of Plutonium-238 at the High Flux Isotope Reactor CJ Hurt, JD Freels, RW Hobbs, PK Jain, GI Maldonado Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High Flux …, 2016 | 7 | 2016 |
| Application of COMSOL Pipe Flow Module To Develop a High Flux Isotope Reactor (HFIR) System Loop Model D Wang, PK Jain, JD Freels COMSOL Conference, Boston, 2013 | 7 | 2013 |
| Investigation of plenum-to-plenum heat transfer and gas dynamics under natural circulation in a scaled-down dual channel module mimicking prismatic VHTR core using CFD MT Kao, P Jain, S Usman, IA Said, MM Taha, MH Al-Dahhan, U Rizwan International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015 | 6 | 2015 |
| 3D COMSOL Simulations for Thermal Deflection of HFIR Fuel Plate in the “Cheverton-Kelley” Experiments PK Jain, JD Freels, DH Cook ORNL/TM-2012/138, 2012 | 6 | 2012 |
Dean WangOhio State UniversityVerified email at osu.edu
