Matthew Jessee Senior R&D Staff, Power Reactor Modeling, Acting Group Lead Contact JESSEEMA@ORNL.GOV All Publications Methods and Usability Enhancements in Shift for Non-LWR Applications Application of Markov Chain Monte Carlo Methods for Uncertainty Quantification in Inverse Transport Problems... Lattice physics calculations using the embedded self-shielding method in polaris, Part II: Benchmark assessment Lattice Physics Calculations Using the Embedded Self-Shielding Method in Polaris, Part I: Methods and Implementation Applications of VERA for Improvement in NRC Methods SCALE Code System SCALE Lattice Physics Code Assessments of Accident Tolerant Fuel Development of Perturbed MPACT Multigroup Libraries and the Perturbation Methodology for Subgroup Data 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 Unknowns 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 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 Analysis of Watts Bar Nuclear 1 Cycle 1 with SCALE/PARCS... Accuracy and Runtime Improvements with SCALE 6.2 Two-Step Uncertainty Analysis of Watts Bar Nuclear 1 Cycle 1 with SCALE/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
