Douglas Peplow Distinguished R&D Staff Member Contact PEPLOWDE@ORNL.GOV All Publications 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... Advanced Variance Reduction Strategies for Optimizing Mesh Tallies in MAVRIC... Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Page 3 Current page 4 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
