Matthew Jessee Senior R&D Staff, Power Reactor Modeling, Acting Group Lead Contact JESSEEMA@ORNL.GOV All Publications Accuracy and Runtime Improvements with SCALE 6.2 Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System Fiscal Year 2016 Report on SCALE Maintenance and Development (ORNL/SR-2017/152) Development of Generalized Perturbation Theory Capability within the SCALE Code Package VERA Benchmarking Results for KRSKO Nuclear Power Plant Cycle 1... Multigroup Data Processing for the Embedded Self-Shielding Method in SCALE... ROD INTERNAL PRESSURE QUANTIFICATION AND DISTRIBUTION ANALYSIS USING FRAPCON... Uncertainty Quantification for Full-core Steady-state PWR Core Simulation with SCALE and PARCS... Hybrid Reduced Order Modeling for Assembly Calculations Application of the DiffeRential Evolution Adaptive Metropolis (DREAM) Method for Uncertainty Quantification in Inverse Transport Problems Bias and Uncertainty Assessment of Pressurized Water Reactor Fuel Isotopics POLARIS: A New Two-Dimensional Lattice Physics Analysis Capability for the SCALE Code System... 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 Enhancements in SCALE 6.1... Comparison of XSUSA and "Two-Step" Approaches for Full Core Uncertainty Quantification... A Generalized Adjoint Approach for Quantifying Reflector Assembly Discontinuity Factor Uncertainties... Development of a Statistical Sampling Method for Uncertainty Analysis with SCALE 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... Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Current page 3 Page 4 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae 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
