Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... ORNL Report August, 2021
In-Core Neutron Flux, Temperature, and Pressure Instrumentation for the WIRE-21 Experiment in the High Flux Isotope Reactor... Conference Paper June, 2021
Overview of the 2020 SCALE 6.2.4 Validation Report for Radiation Shielding Applications* Conference Paper June, 2021
Studies on Enhanced Spatial Control with Low Enriched Uranium in Plate-Type Fuels Conference Paper June, 2021
Monte Carlo Simulation of Background and Source Measurements with CSG and CAD Geometries ORNL Report June, 2021
Lattice Physics Calculations Using the Embedded Self-Shielding Method in Polaris, Part I: Methods and Implementation Journal January, 2021
