Douglas Peplow Distinguished R&D Staff Member Contact PEPLOWDE@ORNL.GOV All Publications FW-CADIS Method for Global and Semi-Global Variance Reduction of Monte Carlo Radiation Transport Calculations Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling... Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems... Enhancements in SCALE 6.1... Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Labor... Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses Scale 6.1 Enhancements for Nuclear Criticality Safety... Global Evaluation of Prompt Dose Rates in ITER Using Hybrid Monte Carlo/Deterministic Techniques... Application of the ORIGEN Fallout Analysis Tool and the DELFIC Fallout Planning Tool to National Technical Nuclear Forensics ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic and CAD-Based Monte Carlo Methods Monte Carlo Shielding Analysis Capabilities with MAVRIC... Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries... Monte Carlo Shielding Analysis Capabilities with MAVRIC Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data (NUREG/CR-7045, ORNL/TM 2011/12)) Monte Carlo Shielding Analysis Capabilities with MAVRIC Hybrid and Parallel Domain-Decomposition Methods Development to Enable Monte Carlo for Reactor Analyses... Review of Hybrid (Deterministic/Monte Carlo) Radiation Transport Methods, Codes, and Applications at Oak Ridge National Labor... Automated Variance Reduction Applied to Nuclear Well-Logging Problems Criticality Accident Alarm System Modeling with SCALE... SIMULTANEOUS OPTIMIZATION OF TALLIES; IN DIFFICULT SHIELDING PROBLEMS... Development and Testing of ENDF/B-VI.8 and ENDF/B-VII.0 Coupled Neutron-Gamma Libraries for SCALE 6 (NUREG/CR-6990, ORNL/TM-2008/047) Automated Variance Reduction Applied to Nuclear Well-Logging Problems MULTIDIMENSIONAL COUPLED PHOTON-ELECTRON TRANSPORT SIMULATIONS USING NEUTRAL PARTICLE SN CODES... Pagination First page « First Previous page ‹‹ … Page 3 Current page 4 Page 5 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
Research Highlight Analyses of key problems strengthen confidence in ORNL's new Shift Monte Carlo code
