A GENERALIZED METHOD FOR CHARACTERIZATION OF 235U AND 239PU CONTENT USING SHORT-LIVED FISSION PRODUCT GAMMA SPECTROSCOPY... Journal October, 2016
A Generalized Method for Fissile Material Characterization Using Short-Lived Fission Product Gamma Spectroscopy Thesis / Dissertation September, 2016
Tritium Content in and Release from Pressurized Water Reactor Fuel Cladding... Conference Paper June, 2016
A GENERALIZED METHOD FOR FISSILE MASS CHARACTERIZATION USING SHORT-LIVED FISSION PRODUCT GAMMA MEASUREMENTS... Conference Paper May, 2016
Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation Journal January, 2016
Radiolytic Treatment of the Next-Generation Caustic-Side Solvent Extraction (NGS) Solvent and its Effect on the NGS Process Journal December, 2014
Tritium Behavior in Zircaloy Cladding from Used Light Water Reactor Fuel Rods... Conference Paper March, 2014
