Robert A Lefebvre Senior R&D Staff - Group Leader Contact lefebvrera@ornl.gov | 865.241.0496 All Publications Shielding Analysis Capability of UNF-ST&DARDS... ORIGAMI: A New SCALE Interface for Fuel Assembly Characterization with ORIGEN... Containment Analysis Capability of UNF-ST&DARDS... CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND... A Unified Spent Nuclear Fuel Database and Analysis System... Criticality Safety Assessment for As-loaded Spent Fuel Storage and Transportation Casks... MODERNIZATION STRATEGIES FOR SCALE 6.2... Streamlining Analysis Capabilities for SNF Management... Integrated Data and Analysis Tool for Used Nuclear Fuel Management... Application of the DiffeRential Evolution Adaptive Metropolis (DREAM) Method for Uncertainty Quantification in Inverse Transp... POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System... Modernization Enhancements in SCALE 6.2... SCALE Enhancements for Detailed Cask Dose Rate Analysis... The Used Nuclear Fuel Storage, Transportation, and Disposal Analysis Resource and Data System... Dose Rate Analysis Capability for Actual Spent Fuel Transportation Cask Contents... POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System OVERVIEW OF SCALE 6.2... Integrated Data and Analysis System for Commercial Used Nuclear Fuel Safety Assessments... Multiphysics Simulations for LWR Analysis... Integrating Data and Analysis Capabilities for Cask-Specific Safety Evaluations... Enhancements in SCALE 6.1... Scale 6.1 Enhancements for Nuclear Criticality Safety... Scale/TSUNAMI Sensitivity Data for ICSBEP Evaluations... The VIBE Tool of SCALE--Validation, Interpretation, and Bias Estimation... Pagination First page « First Previous page ‹‹ Page 1 Page 2 Current page 3 Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Modeling and Simulation Development and Deployment Section Nuclear Code Integration Group SCALE