Tritium Content in and Release from Pressurized Water Reactor Fuel Cladding... Conference Paper June, 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
ADAPTATION OF HPLC-ICPMS MEASUREMENT PROTOCOLS FOR NUCLEAR PROJECTS AT THE OAK RIDGE NATIONAL LABORATORY Conference Paper August, 2013
