Determining Cooling Time to Improve Burnup Estimation for Characterizing Reactor Operations Conference Paper September, 2024
National Nuclear Materials Archive Program at the Oak Ridge National Laboratory Conference Paper July, 2024
Determination of intermediates and products of the uranyl aerosol formation in UF6 hydrolysis in the gas phase Journal April, 2024
Sub-Pin Fission Product Sensitivity to Assembly and Core Models on High Burnup Fuel and Comparison to Experimental Measurements Conference Paper April, 2024
Density Measurements of Various Molten Sodium, Magnesium, Potassium, and Uranium Chloride Salt Compositions Using Neutron Imaging Journal November, 2022
Production Cycle Characteristics and Timelines for National Nuclear Materials Archive Conference Paper September, 2022
Preservation of National Nuclear Materials Archive Specimens at Oak Ridge National Laboratory Conference Paper September, 2022
Real-Time Inventory Change Detection for the Protactinium Decay Inventory of the Molten Salt Breeder Reactor Journal September, 2022
