Heat deposition analysis for the High Flux Isotope Reactor’s HEU and LEU core models Journal October, 2017
Additional Capability Being Developed from UNF-ST&DARDS Unified Database: System Analysis and Fuel Cycle Option Analysis... Journal September, 2017
Integral nuclear data validation using experimental spent nuclear fuel compositions... Journal September, 2017
A Lumped Parameter MOC Approach and Multigroup Kernels Applied to the Subgroup Self-Shielding Calculation in MPACT Journal September, 2017
Development of Streamlined Nuclear Safety Analyses for Used Nuclear Fuel Applications Journal September, 2017
Sensitivity Analysis for Best-Estimate Thermal Models of Vertical Dry Cask Storage Systems Journal August, 2017
