W. David Pointer
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View article: Investigation of Point-Contact Strategies for CFD Simulations of Pebble-Bed Reactor Cores
Investigation of Point-Contact Strategies for CFD Simulations of Pebble-Bed Reactor Cores Open
This study numerically investigated the effects of various contact strategies on the thermal hydraulic behavior within a structured bed of 100 explicitly modeled pebbles. Four contact strategies and two thermal hydraulic conditions were co…
View article: The infrastructure powering IBM's Gen AI model development
The infrastructure powering IBM's Gen AI model development Open
AI Infrastructure plays a key role in the speed and cost-competitiveness of developing and deploying advanced AI models. The current demand for powerful AI infrastructure for model training is driven by the emergence of generative AI and f…
View article: Final CRADA Report – NFE-21-08642Multiphysics Design Optimization and Additive Manufacturing of Nuclear Components (Executive Summary)
Final CRADA Report – NFE-21-08642Multiphysics Design Optimization and Additive Manufacturing of Nuclear Components (Executive Summary) Open
Westinghouse Electric Company (WEC) actively participated in the advancement of the nuclear fuel and reactor design space and requested the help of Oak Ridge National Laboratory (ORNL) in the creation of a new design tool set. This report …
View article: Interface Capturing Simulations on Pool Boiling Performance With Multiple Nucleation Sites
Interface Capturing Simulations on Pool Boiling Performance With Multiple Nucleation Sites Open
High-fidelity pool boiling simulations can provide a numerical database for improving mechanistic boiling models by allowing for specific evaluation of interactions among bubbles. Previously published pool boiling simulations investigated …
View article: Eulerian Two-Fluid RANS-based CFD Simulations of a Helical Coil Steam Generator Boiling Tube
Eulerian Two-Fluid RANS-based CFD Simulations of a Helical Coil Steam Generator Boiling Tube Open
As part of a larger effort to demonstrate a simulation-based capability for the evaluation and optimization of helical coil steam generators, the performance of a helical coil steam generator tube is being considered using a Eulerian two-f…
View article: Volume 10: Flow Test Facilities
Volume 10: Flow Test Facilities Open
Adding additional flow testing facilities has been considered as part of the High Flux Isotope Reactor (HFIR) Sustaining and Enhancing Neutron Science (SENSe) Initiative at Oak Ridge National Laboratory (ORNL) to support HFIR operations an…
View article: Computational Fluid Dynamics Modeling to Simulate a Combined Reforming Process for Syngas and Hydrogen Production
Computational Fluid Dynamics Modeling to Simulate a Combined Reforming Process for Syngas and Hydrogen Production Open
An Oxygen Transport Membrane (OTM) combined reforming technology for producing syngas and hydrogen integrates the advantages of multiple processes—steam methane reforming (SMR), autothermal reforming (ATR), an air separation unit (ASU)—int…
View article: Coupling of CTF and TRANSFORM using the Functional Mockup Interface
Coupling of CTF and TRANSFORM using the Functional Mockup Interface Open
An in-memory coupling between the sub-channel thermal hydraulics code COBRA-TF (CTF), which is included in the Virtual Environment for Reactor Applications (VERA), and the systems code Transient Simulation Framework of Reconfigurable Model…
View article: Simulation of Boiling Two-Phase Flow in a Helical Coil Steam Generator Using the Spectral Element Code Nek-2P
Simulation of Boiling Two-Phase Flow in a Helical Coil Steam Generator Using the Spectral Element Code Nek-2P Open
To enable the design of a light water small modular reactor, the boiling flow inside a helical coil steam generator has been simulated with the two-fluid model in Nek-2P. Nek-2P is the multiphase branch of the spectral element code Nek5000…
View article: Integration of the Nek5000 Computational Fluid Dynamics Code with the NEAMS Workbench
Integration of the Nek5000 Computational Fluid Dynamics Code with the NEAMS Workbench Open
The mission of the US Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program is to develop, apply, deploy, and support state-of-the-art predictive modeling and simulation tools for the design and analysis of…
View article: Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF
Implementation of a Spacer Grid Rod Thermal-Hydraulic Reconstruction (ROTHCON) Capability into the Thermal-Hydraulic Subchannel Code CTF Open
The Consortium for Advanced Simulation of Light Water Reactors is developing a core simulator capability known as the Virtual Environment for Reactor Applications (VERA) to address nuclear industry challenge problems such as crud-induced p…
View article: Technologies to Reactors: Enabling Accelerated Deployment of Nuclear Energy Systems Workshop Report
Technologies to Reactors: Enabling Accelerated Deployment of Nuclear Energy Systems Workshop Report Open
Nuclear energy provides almost 20% of the electric power in the United States, producing power with high availability while accounting for 63% of our carbon-free energy production. While we have the capacity to expand this clean power sour…
View article: ONRAMP, ORNL Nuclear Resources Analysis and Modeling Portfolio
ONRAMP, ORNL Nuclear Resources Analysis and Modeling Portfolio Open
Many teams from US and international organizations, government, industry, research organizations, and academic institutions have established near-term technical exchanges and long-term partnerships with ORNL, realizing previously unforesee…
View article: High Performance Computational Models of Synthetic Jet Actuators for Step Change Improvements in Freight Efficiency
High Performance Computational Models of Synthetic Jet Actuators for Step Change Improvements in Freight Efficiency Open
The project presents results of a computational fluid dynamics (CFD) model developed by the Oak Ridge National Laboratory team for a synthetic jet produced by an actuator. Numerical results were compared against experimental data provided …
View article: An Uncertainty Quantification of the Computational Fluid Dynamics Solution to the Modeling of the Contact Point in a Wire-Wrapped Fuel Assembly
An Uncertainty Quantification of the Computational Fluid Dynamics Solution to the Modeling of the Contact Point in a Wire-Wrapped Fuel Assembly Open
An uncertainty quantification and sensitivity analysis of the turbulent flow in a wire-wrapped pin bundle to the contact-point model and the inlet conditions is presented. Three geometries are considered in this work that are an infinitely…
View article: Report on UQ Assessments to support SESAME wire-wrapped bundle experiment
Report on UQ Assessments to support SESAME wire-wrapped bundle experiment Open
This work assesses the influence of assumptions made when generating a mesh of a wire-wrapped geometry. The contact region between a wire and its adjacent pin is commonly modeled by either embedding the wire to the adjacent pin or trimming…
View article: Reference Computational Meshing Strategy for Computational Fluid Dynamics Simulation of Departure from Nucleate Boiling
Reference Computational Meshing Strategy for Computational Fluid Dynamics Simulation of Departure from Nucleate Boiling Open
The objective of this effort is to establish a strategy and process for generation of suitable computational mesh for computational fluid dynamics simulations of departure from nucleate boiling in a 5 by 5 fuel rod assembly held in place b…