Use of Risk Management in Implementing the Mark-18A Target Material Recovery Program... Conference Paper July, 2016
Tritium Content in and Release from Pressurized Water Reactor Fuel Cladding... Conference Paper June, 2016
ORNL Experience and Perspectives Related to Processing of Thorium and U-233 for Nuclear Fuel Journal May, 2016
Processing and Disposition of Remote Handled Transuranic Liquid Waste Generated at 91°µÍø... Conference Paper March, 2016
Determining Initial Enrichment, Burnup, and Cooling Time of Pressurized-Water Reactor Spent Fuel Assemblies by Analyzing Pass... Journal February, 2016
Calculation of the 240Pu-Effective Coefficients for Neutron Correlation Counting - INMM... Conference Paper July, 2015
