Matthew A Jessee Senior R&D Staff, Power Reactor Modeling, Acting Group Lead Contact jesseema@ornl.gov | 865.241.1503 All Publications Initial Application of TSUNAMI for Validation of Advanced Fuel Systems Application of Markov Chain Monte Carlo for Uncertainty Quantification in Quantitative Imaging Problems Preliminary TSUNAMI Assessment of the Impact of Accident Tolerant Fuel Concepts on Reactor Physics Validation... Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark... Uncertainty Analysis for Neutron Active Interrogation Calculations... Application of Polynomial Chaos Expansion in Inverse Transport Problems with Neutron Multiplication Measurements and Multiple... Uncertainty Quantification of Pressurized Water Reactor Coupled Core Simulation Using Stochastic Sampling Method... SCALE 6.2 REACTOR PHYSICS CODE ACCURACY ASSESMENT FOR LIGHT WATER REACTOR FUEL... Improvements in the Polaris Implementation of the Embedded Self-Shielding Method... Application of Polynomial Chaos Expansion in Inverse Transport Problems with Neutron Multiplication Measurements and Multiple Unknowns Determining Physical Parameters of Shielded Uranium using Gamma Spectroscopy and the DiffeRential Evolution Adaptive Metropolis (DREAM) Method BWR Geometry Enhancements for the Polaris Lattice Physics Code... Two-Step Analysis of Watts Bar Nuclear 1 Cycle 1 with SCALE/PARCS... Sensitivity Coefficients for Diffusion Coefficients and Other Reactor Physics Parameters using CE TSUNAMI-3D ... Determining physical parameters of shielded uranium using gamma spectroscopy and the DiffeRential Evolution Adaptive Metropol... Two-Step Uncertainty Analysis of Watts Bar Nuclear 1 Cycle 1 with SCALE/PARCS... 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... Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 Next page ›› Last page Last » 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