Brandon R Grogan Nuclear Chemical Engineer Contact groganbr@ornl.gov | 865.576.7468 All Publications Fuel Assembly Reference Information for SNF Radiation Source Term Calculations Safeguards Technology for Thorium Fuel Cycles: Research and Development Needs Assessment and Recommendations... Safeguards Challenges and Safeguards Technology Needs Assessment for Leading Thorium Fuel Cycles... Reconstructing Reactor Operating Histories Using the INDEPTH Code... Verifying Safeguards Declarations with INDEPTH: A Sensitivity Study Reconstructing Reactor Operating Histories Using the INDEPTH Code Verifying Safeguards Declarations with INDEPTH: A Sensitivity Study... Sensitivity Study of INDEPTH for Verification of Facility Spent Nuclear Fuel Declarations... PWR and BWR spent fuel assembly gamma spectra measurements... NDA Measurement Analysis of Spent Nuclear Fuel Assemblies at the Swedish Clab Facility Using the INDEPTH Code... Passive Gamma Analysis of the Boiling-Water-Reactor Assemblies... Determining Initial Enrichment, Burnup, and Cooling Time of Pressurized-Water Reactor Spent Fuel Assemblies by Analyzing Pass... Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden Investigation of Active Interrogation Techniques to Detect Special Nuclear Material in Maritime Environments: Boarded Search... Investigations of Active Interrogation Techniques to Detect Special Nuclear Material in Maritime Environments: Standoff Inter... Fast-Neutron Imaging with API DT Neutron Generators... Identification of Lithium Isotopes Using Time-Tagged Neutron Scattering... Attributes from NMIS Time Coincidence, Fast-Neutron Imaging, Fission Mapping, And Gamma-Ray Spectrometry Data... Simulating NMIS Imaging and Fission-Mapping Measurements... Neutron Radiography and Fission Mapping Measurements of Nuclear Materials with Varying Composition and Shielding... Identification of Shielding Material Configurations Using NMIS Imaging... The Development of a Parameterized Scatter Removal Algorithm for NMIS Imaging... The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging... Measurements of 14.1 MeV Neutron Reflection and Transmission for Carbon, Polyethylene, and Steel... Simulated Verification of Fuel Element Inventory in a Small Reactor Core Using the Nuclear Materials Identification System (N... Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Curriculum Vitae ORCID Organizations National Security Sciences Directorate Nuclear Nonproliferation Division Nonproliferation Engineering Science and Technologies Section Material Security and Counterproliferation Group
