Douglas E Peplow Distinguished R&D Staff Member Contact 865.574.0521 | peplowde@ornl.gov All Publications A Comparison of the FW-CADIS and MR-CADIS Variance Reduction Methods... Characterization of NORM in an Urban Environment using HPGe Measurements and MCNP6 Simulations... Initial Modeling of Urban Search Measurements NORM Concentration Determination in Common Materials in an Urban Environment... The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation... Shutdown Dose Rate Analysis Using the Multi-Step CADIS Method... CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems... Monte Carlo Capabilities of the SCALE Code System... Analysis of Shutdown Dose Rate in Fusion Energy Systems Using Hybrid Monte Carlo/Deterministic Techniques ACCELERATION OF SHUTDOWN DOSE RATE MONTE CARLO CALCULATIONS USING THE MULTI-STEP CADIS HYBRID METHOD Enhancements in Continuous-Energy Monte Carlo Capabilities for SCALE 6.2... Comparison of ADVANTG Simulations to Simple Shielding Measurements... SCALE Enhancements for Detailed Cask Dose Rate Analysis Dose Rate Analysis of As-Loaded Spent Nuclear Fuel Casks... Identification of Leakage Spectra from Neutron Activation in Glass/Cherenkov Detectors Analysis of Shutdown Dose Rate in Fusion Energy Systems Using Hybrid Monte Carlo/Deterministic Techniques... The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents Monte Carlo Capabilities of the SCALE Code System... Novel Hybrid Monte Carlo/Deterministic Technique for Shutdown Dose Rate Analyses of Fusion Energy Systems GUIDANCE DETAILING METHODS TO CALCULATE CRITICALITY ACCIDENT ALARM SYSTEM DETECTOR RESPONSE AND COVERAGE... OVERVIEW OF SCALE 6.2 Enhancements in Continuous-Energy Monte Carlo Capabilities in SCALE... Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis... Pagination Current page 1 Page 2 Page 3 … Next page ›› Last page Last » Key Links Curriculum Vitae ORCID 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
