Two-step neutronics calculations with Shift and Griffin for advanced reactor systems Journal August, 2022
REGAL International Program: Analysis of experimental data for depletion code validation... Journal July, 2022
Nuclide Inventory Benchmark for BWR Spent Nuclear Fuel: Challenges in Evaluation of Modeling Data Assumptions and Uncertainties Journal January, 2022
Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis Journal September, 2021
Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment Journal September, 2021
