Ahmad Ibrahim Senior Neutronics Scientist Contact IBRAHIMAM@ORNL.GOV All Publications Analysis of Second Target Station Target Streaming in Support of the Preliminary Design of the Target Assembly... Overview of Shielding Analyses at 91°µÍø’s Spallation Neutron Source Second Target Station... Evaluation of Second Target Station Target Streaming for the Preliminary Design of the Target Assembly Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG A... Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration Analysis of Radiation Transport Due to Activated Coolant in the ITER Neutral Beam Injection Cell Acceleration of Calculation of Nuclear Heating Distributions in ITER Toroidal Field Coils Using Hybrid Monte Carlo/Determinis... Assessing the Multi-Step CADIS Parameters for the Efficient Implementation in Shutdown Dose Rate Analysis The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation... Shutdown Dose Rate Analysis Using the Multi-Step CADIS Method... Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Difficult Shielding Problems... CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND Monte Carlo Capabilities of the SCALE Code System... Analysis of Shutdown Dose Rate in Fusion Energy Systems Using Hybrid Monte Carlo/Deterministic Techniques ACCELERATING FUSION REACTOR NEUTRONICS MODELING BY AUTOMATIC COUPLING OF HYBRID MONTE CARLO/DETERMINISTIC TRANSPORT ON CAD GE... ACCELERATION OF SHUTDOWN DOSE RATE MONTE CARLO CALCULATIONS USING THE MULTI-STEP CADIS HYBRID METHOD The Multi-Step CADIS Method for Shutdown Dose Rate Calculations and Uncertainty Propagation Analysis of Shutdown Dose Rate in Fusion Energy Systems Using Hybrid Monte Carlo/Deterministic Techniques... Monte Carlo Capabilities of the SCALE Code System... Novel Hybrid Monte Carlo/Deterministic Technique for Shutdown Dose Rate Analyses of Fusion Energy Systems Automatic Mesh Adaptivity for Hybrid Monte Carlo/Deterministic Neutronics Modeling of Fusion Energy Systems... Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis... Propagation of Uncertainty from a Source Computed with Monte Carlo Novel Hybrid Monte Carlo/Deterministic Technique for Shutdown Dose Rate Calculations AUTOMATIC MESH ADAPTIVITY FOR CADIS AND FW-CADIS NEUTRONICS MODELING OF DIFFICULT SHIELDING PROBLEMS... Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae Organizations Neutron Technologies Division Neutron Instrument Technologies (RP) Section Neutronics Group
