Douglas Peplow Distinguished R&D Staff Member Contact PEPLOWDE@ORNL.GOV All Publications Generation of Synthetic Data for a Radiation Detection Algorithm Competition Official Release of The Radioisotope Power System Dose Estimation Tool (RPS-DET) Specific Gamma-Ray Dose Constants with Current Emission Data Attribution of gamma-ray background collected by a mobile detector system to its surroundings using panoramic video Preliminary Validation of the Shift Monte Carlo Code for Fixed-Source Radiation Transport Problems Radioisotope Power System Dose Estimation Tool (RPS-DET) User Manual A Directional Detector Response Function for Anisotropic Detectors Validation of the Shift Monte Carlo Code – Neutron Field Measurements in a Concrete Labyrinth... Uncertainty Analysis for Neutron Active Interrogation Calculations... Detailed SCALE Dose Rate Evaluations for a Consolidated Interim Spent Nuclear Fuel Storage Facility A Methodology for Determining the Concentration of Naturally Occurring Radioactive Materials in an Urban Environment Initial Modeling of Urban Search Measurements Application of the ORIGEN Fallout Analysis Tool and the DELFIC Fallout Planning Tool to National Technical Nuclear Forensics A Methodology for Determining the Concentration of Naturally Occurring Radioactive Materials in an Urban Environment Forward-Weighted CADIS Method for Variance Reduction of Monte Carlo Calculations of Distributions and Multiple Localized Quantities Guide to Performing Computational Analysis of Criticality Accident Alarm Systems ORNL/TM-2013-211 Advanced Variance Reduction Strategies for Optimizing Mesh Tallies in MAVRIC Criticality Accident Alarm System Modeling with SCALE Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries Monaco/MAVRIC: Computational Resources for Radiation Protection and Shielding in SCALE Multiagency Urban Search Experiment Detector and Algorithm Test Bed Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation Monte Carlo Capabilities of the SCALE Code System FW-CADIS Method for Global and Semi-Global Variance Reduction of Monte Carlo Radiation Transport Calculations Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Current page 3 Page 4 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 Data, Criticality Safety, and Radiation Transport Section Radiation Transport Group SCALE
