Eva E Davidson Group Leader, Reactor and Nuclear Fuel Cycle Analysis Contact 865.576.0575 | DAVIDSONEE@ORNL.GOV All Publications Demonstration and Preliminary Validation of Griffin for MSR Depletion with Chemical Removal Parametric Studies... The importance of delayed neutron precursors in gamma dose calculations for activated primary heat exchanger components in the Molten Salt Breeder Reactor Griffin's Depletion Calculation of Molten Salt Reactor Experiment Effects of Neutron Irradiation on the Structural Performance of the Concrete Biological Shield in Light Water Reactors Non-LWR Fuel Cycle Scenarios for SCALE and MELCOR Modeling Capability Demonstration Molten Salt Reactor Experiment Simulation using Shift/Griffin Modeling and Simulation of Xe-100 type Pebble Bed Gas-Cooled Reactor with SCALE Assessing UN Neutronic and Fuel Performance for Extended Cycle Lengths... A Structural Model of the Long-term Degradation of the Concrete Biological Shield Final Summary Report on the Feasibility and the Benefits of the Advanced Nuclear Fuel Pellet Designs with Radially Varying Fu... Reactor Physics Characteristics of High Flux Isotope Reactor Core Designs with Low-Enriched Uranium Fuels High Flux Isotope Reactor Low Enriched Uranium U-10Mo Fuel Design Parameters VERA User's Guide for Ex-core Applications Reactor Cell Neutron Dose for the Molten Salt Breeder Reactor Conceptual Design... Validation of Light Water Reactor Ex-Core Calculations with VERA VERA-Grizzly Ex-Core Calculations: Watts Bar Unit 1 Cycles 1-2... Demonstration of Comprehensive Ex-Vessel Fluence Capability Benchmarking Of Source Range Detector Responses During Watts Bar Unit 1 Refueling Secondary-Source Core Reload Modeling with VERA Validation of VERA Ex-core Detector Response Calculations for Shearon Harris Reassessing Methods to Close the Nuclear Fuel Cycle Benchmarking VERA for Criticality and Depletion Calculations of Accident Tolerant Fuels Modeling and Simulation of a High Flux Isotope Reactor Representative Core Model for Updated Performance and Safety Basis Assessments High-Fidelity Ex-core Capabilities in VERA Effect of Fission Source Spectrum on Monte Carlo Calculation of Ex-Core Quantities Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Applications, Methods, and Data Section Reactor and Nuclear Fuel Cycle Analysis Group SCALE User Facilities High Flux Isotope Reactor Oak Ridge Leadership Computing Facility
