Gregory Davidson Research and Development Staff Contact 865.574.3921 | DAVIDSONGG@ORNL.GOV All Publications Status of GPU capabilities within the Shift Monte Carlo radiation transport code Assessing the Consequences of Postclosure Criticality in Spent Nuclear Fuel Status of Multiphysics Modeling of Critical DPCs in a Geological Repository... Weight window variance reduction on GPUs in the Shift Monte Carlo Code Layered CAD/CSG geometry for spatially complex radiation transport scenarios A Parametric Study of Criticality in Dual-Purpose Canisters for Long-Term Disposal Validation of Thermohydraulic Simulations using RELAP for Critical Dual Purpose Canisters Insert Modeling in UNF ST&NDARDS Multiphysics modeling of a critical dual-purpose canister in a saturated geological repository Layered CAD/CSG Geometry for Neutronics Modeling of Advanced Reactors... Preliminary Assessment of as-Built Design Characteristics for the Transformational Challenge Reactor Photon detector response function methodology using MCNP and shift hybrid radiation transport code for wide-area contamination assay applications Monte Carlo Simulation of Background and Source Measurements with CSG and CAD Geometries Choosing Transport Events for Initiating Splitting and Rouletting... As-Built Simulation of the High Flux Isotope Reactor Secondary-Source Core Reload Modeling with VERA Omnibus User Manual As-Built Simulation of the High Flux Isotope Reactor Singular value decomposition of adjoint flux distributions for Monte Carlo variance reduction Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing Development of Terrenus: A Multiphysics Code for Spent Nuclear Fuel Canister Criticality Analysis... Development of Terrenus, a Multiphysics Code for Spent Nuclear Fuel Cask Criticality Analysis Source Range Detector Response Modeling using VERA Initial Neutronics and Thermal-Hydraulic Coupling for Spent Nuclear Fuel Canister... Pagination Current page 1 Page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Modeling and Simulation Development and Deployment Section HPC Methods for Nuclear Applications Group User Facilities SCALE
