W. David Pointer Director, Nuclear Energy and Fuel Cycle Division Contact pointerwd@ornl.gov | 865.241.4472 All Publications CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pre... High-fidelity pool boiling simulations on multiple nucleation sites using interface capturing method... The pursuit of net-positive sustainability for industrial decarbonization with hybrid energy systems... Investigation of Point-Contact Strategies for CFD Simulations of Pebble Bed Reactor Cores... Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF Digital Twins for Nuclear Power Plants and Facilities Volume 10: Flow Test Facilities The Role of Hybrid Energy Systems in Decarbonizing Industry: A Carbon Handprint–Based Case Study... Interface Capturing Simulations on Pool Boiling Performance With Multiple Nucleation Sites... Computational Fluid Dynamics Modeling to Simulate a Combined Reforming Process for Syngas and Hydrogen Production... Coupling of CTF and TRANSFORM using the Functional Mockup Interface... Development of a Crud Induced Localized Corrosion Analysis Capability in VERA... Solution Verification and Spatial Uncertainty Quantification for CFD Simulations of Nuclear Fuel Bundle Flows Simulation of Boiling Two-Phase Flow in a Helical Coil Steam Generator Using the Spectral Element Code Nek-2P Integration of the Nek5000 Computational Fluid Dynamics Code with the NEAMS Workbench ONRAMP, ORNL Nuclear Resources – Analysis and Modeling Portfolio An Uncertainty Quantification of the Computational Fluid Dynamics Solution to the Modeling of the Contact Point in a Wire-Wra... Integration of the Nek5000 Computational Fluid Dynamics Code to the NEAMS Workbench... Implementation of a grid heat transfer HI2LO reconstruction capability into the thermal hydraulics subchannel code CTF... Jet stability and wall impingement flow field in a thermal striping experiment... Eulerian Two-Fluid RANS-based CFD Simulations of a Helical Coil Steam Generator Boiling Tube... Dakota Uncertainty Quantification Methods Applied to the CFD Code Nek5000 Jet stability and wall impingement flow field in a thermal striping experiment Dakota Uncertainty Quantification Methods Applied to the CFD code Nek5000... TAKING A FRESH LOOK AT BOILING HEAT TRANSFER ON THE ROAD TO IMPROVED NUCLEAR ECONOMICS AND EFFICIENCY... Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division