Shutdown dose rate analysis with the Shift Monte Carlo radiation transport code and modular verification workflow Journal September, 2023
Microstructural characterization of the CGB graphite grade from the molten salt reactor experiment Journal August, 2023
ASSESSMENT OF EXISTING TRANSPORTATION PACKAGES FOR USE WITH LEU+ AND HALEU MATERIAL Conference Paper August, 2023
High Flux Isotope Reactor Irradiation of Self-Powered Neutron Detectors Conference Paper August, 2023
SCALE Modeling of the Sodium Cooled Fast-Spectrum Advanced Burner Test Reactor ORNL Report July, 2023
Measurement of the neutron-induced capture-to-fission cross section ratio in 233U at LANSCE Journal July, 2023
Preliminary Design of Critical Experiments Involving Commercially available B4C Neutron Absorber Plates with Low-Enriched UO2 fuel Conference Paper July, 2023
