Matthew Jessee Senior R&D Staff, Power Reactor Modeling, Acting Group Lead Contact JESSEEMA@ORNL.GOV All Publications Polaris-PARCS Sensitivity Study on LWR Fuel Cycles: Polaris Input Options Reassessment of Boiling Water Reactor Rod Cusping Capability of VERA-MPACT Modeling Enhancements, Cross-Section Generation Updates, and Benchmarking with Shift FY24 Mole Development Updates and SAM-Mole Coupling for MSR Species Transport Applications... NEAMS Reactor Physics Project Management and Coordination Activities... Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor Benchmark Calculations for Turkey Point Unit 3 and Surry Unit 1 using the SCALE/Polaris--PARCS Procedure Sensitivity Analysis of the SCALE/Polaris-PARCS Code Procedure for Watts Bar Unit 1 and Peach Bottom Unit 2 Dancoff-Based Wigner-Seitz Approximation for the Embedded Self-Shielding Method in SCALE/Polaris Modeling Enhancements and Benchmarking of Pebble Bed Reactors in the Shift Monte Carlo Code Coupled neutronics and species transport simulation of the Molten Salt Reactor Experiment Parameters of Neutron Diffusion Equation for Temperature Effect of MSRE Heat and Mass Transfer Coefficients in the Molten Salt Reactor Experiment Modeling Enhancements and Demonstration of Shift Capabilities for PBR and MSR Benchmark Calculations for Peach Bottom Unit 2 and Hatch Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package Benchmark Calculations for BEAVRS and Watt Bar Unit 1 Using the SCALE-6.3.0/Polaris-PARCS v3.4.2 Code Package... Multiphysics Mass Accountancy Calculation for Noble Metals Tracking in MSRE Loop SCALE Lattice Physics Performance Assessment Modeling, Performance Assessment, and Nodal Data Analysis of TRISO-Fueled Systems with Shift Two-step neutronics calculations with Shift and Griffin for advanced reactor systems Dancoff-Based Wigner-Seitz Approximation for the Subgroup Resonance Self-Shielding in the VERA Neutronics Simulator MPACT VERA Enhancements for Cross Section Shielding and Geometry Capabilities Cell Dancoff-Based Embedded Self-Shielding Capability for Doubly Heterogeneous Particulate Fuels in SCALE/Polaris Transient convective delayed neutron precursors of 235U for the Molten Salt Reactor Experiment... Revisit of the Dancoff-Based Wigner-Seitz Approximation for Pointwise and Multigroup Resonance Self-Shielding Calculations in SCALE Pagination Current page 1 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
