Matthew A Jessee Senior R&D Staff, Power Reactor Modeling, Acting Group Lead Contact jesseema@ornl.gov | 865.241.1503 All Publications Hybrid Reduced Order Modeling for Assembly Calculations... 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... Bias and Uncertainty Assessment of Pressurized Water Reactor Fuel Isotopics... POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA... Application of Generalized Linear Least-Squares for Uncertainty Quantification in Inverse Transport Problems... Hybrid Reduced Order Modeling for Assembly Calculations... A Statistical Sampling Method for Uncertainty Analysis with SCALE and XSUSA A Generalized Adjoint Approach for Quantifying Reflector Assembly Discontinuity Factor Uncertainties... Development of a Statistical Sampling Method for Uncertainty Analysis with SCALE... Enhancements in SCALE 6.1... Comparison of XSUSA and "Two-Step" Approaches for Full Core Uncertainty Quantification... A Two-Step Approach to Uncertainty Quantification of Core Simulators... Many-Group Cross-Section Adjustment Techniques for Boiling Water Reactor Adaptive Simulation... Scale 6.1 Enhancements for Nuclear Criticality Safety... Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE... Sensitivity and Uncertainty Analysis Capabilities and Data in SCALE Development and validation of scale nuclear analysis methods for high temperature gas-cooled reactors... Development of Generalized Perturbation Theory Capability within the SCALE Code Package... Pagination First page « First Previous page ‹‹ Page 1 Page 2 Current page 3 Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Modeling and Simulation Development and Deployment Section Power Reactor Modeling Group SCALE