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 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... Scale 6.1 Enhancements for Nuclear Criticality Safety... Application of the ORIGEN Fallout Analysis Tool and the DELFIC Fallout Planning Tool to National Technical Nuclear Forensics Global Evaluation of Prompt Dose Rates in ITER Using Hybrid Monte Carlo/Deterministic Techniques... 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 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)) 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
Research Highlight Analyses of key problems strengthen confidence in ORNL's new Shift Monte Carlo code
