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 Integration of the Nek5000 Computational Fluid Dynamics Code to the NEAMS Workbench... An Uncertainty Quantification of the Computational Fluid Dynamics Solution to the Modeling of the Contact Point in a Wire-Wra... 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
