Gregory Davidson
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View article: Status of GPU capabilities within the Shift Monte Carlo radiation transport code
Status of GPU capabilities within the Shift Monte Carlo radiation transport code Open
Shift is a general-purpose Monte Carlo (MC) radiation transport code for fission, fusion, and national security applications. Shift has been adapted to efficiently run on GPUs in order to leverage leadership-class supercomputers. This work…
View article: Assessing the Consequences of Postclosure Criticality in Spent Nuclear Fuel
Assessing the Consequences of Postclosure Criticality in Spent Nuclear Fuel Open
The U.S. Department of Energy is funding research into studying the consequences of postclosure criticality on the performance of a generic repository by (1) identifying the features, events, and processes (FEPs) that need to be considered…
View article: Sweepless time-dependent transport calculations using the staggered block Jacobi method
Sweepless time-dependent transport calculations using the staggered block Jacobi method Open
The Staggered-Block Jacobi (SBJ) method is a new numerical SN transport method for solving time-dependent problems without sweeps or low-order acceleration. Because it is a Jacobian method, it is trivial to parallelize and will scale linea…
View article: Status of Multiphysics Modeling of Critical DPCs in a Geological Repository
Status of Multiphysics Modeling of Critical DPCs in a Geological Repository Open
A summary of previous work focused on the first two scenarios is presented as an established workflow. These canisters could reach an equilibrium at a low quasi–steady-state power level that could be sustained for thousands of years. The m…
View article: Insert Modeling in UNF ST&DARDS
Insert Modeling in UNF ST&DARDS Open
The Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS) is a software tool that integrates a used nuclear fuel (UNF) or spent nuclear fuel (SNF) relational database and key analysis capabil…
View article: Validation of Thermohydraulic Simulations using RELAP for Critical Dual Purpose Canisters
Validation of Thermohydraulic Simulations using RELAP for Critical Dual Purpose Canisters Open
Simulations using the RELAP5-3D systems analysis code and STAR-CCM+, a high-fidelity CFD code, were performed on a model of a real-scale MPC-32 dual purpose canister undergoing a criticality event. These simulations were performed to provi…
View article: Monte Carlo Simulation of Background and Source Measurements with CSG and CAD Geometries
Monte Carlo Simulation of Background and Source Measurements with CSG and CAD Geometries Open
Detecting radioactive sources in an urban environment is difficult due to the large magnitude and variability of the background radiation. To support the search mission of the National Nuclear Security Administration, a project was underta…
View article: Choosing Transport Events for Initiating Splitting and Rouletting
Choosing Transport Events for Initiating Splitting and Rouletting Open
A study was performed to determine which transport events should be used to initiate a weight window lookup to achieve the best variance reduction performance. A weight window lookup potentially triggers particle splitting (in important re…
View article: As-Built Simulation of the High Flux Isotope Reactor
As-Built Simulation of the High Flux Isotope Reactor Open
The Oak Ridge National Laboratory High Flux Isotope Reactor (HFIR) is an 85 MWt flux trap-type research reactor that supports key research missions, including isotope production, materials irradiation, and neutron scattering. The core cons…
View article: Secondary-Source Core Reload Modeling with VERA
Secondary-Source Core Reload Modeling with VERA Open
The CASL reactor simulation package VERA has been adapted to provide high-fidelity simulation capabilities for modeling source range detector response during subcritical reactor configurations. New features include the activation and shuff…
View article: Omnibus User Manual
Omnibus User Manual Open
This manual provides instructions for using Omnibus to run the Exnihilo code suite, which contains the Denovo and Shift transport solvers.
View article: The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing
The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing Open
A new MAVRIC-Shift sequence has been implemented and tested within the SCALE Code System to provide parallel computing capabilities for radiation transport and shielding analysis with automated variance reduction. This new sequence provide…
View article: Initial Neutronics and Thermal-Hydraulic Coupling for Spent Nuclear Fuel Canister
Initial Neutronics and Thermal-Hydraulic Coupling for Spent Nuclear Fuel Canister Open
This report documents work performed supporting the US Department of Energy (DOE) Nuclear Energy Spent Fuel and Waste Disposition, Spent Fuel and Waste Science and Technology, under work breakdown structure element 1.08.01.03.05, “Direct D…
View article: A Directional Detector Response Function for Anisotropic Detectors
A Directional Detector Response Function for Anisotropic Detectors Open
For a radiation detector that is not isotropic, a directional detector response is needed to accurately account for the variation in a detector’s behavior depending on the incoming particle direction. The concept of the detector response f…
View article: Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems
Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems Open
Simulations of neutron and photon transport using the Shift Monte Carlo radiation transport code are compared with experimental measurements and their corresponding benchmark simulations from several sets of experiments. Overall, Shift res…
View article: Criticality Consequence Analysis Roadmap for Spent Nuclear Fuel Canister in a Repository
Criticality Consequence Analysis Roadmap for Spent Nuclear Fuel Canister in a Repository Open
This report discusses an initial criticality consequence analysis approach of commercial spent fuel canisters in a repository that will be developed to support a performance assessment (PA) of a repository with criticality events. A reposi…