Application of the SAMINT methodology to the new cross section evaluations of 63 Cu and 65 Cu ∗ Conference Paper September, 2017
Additional Capability Being Developed from UNF-ST&DARDS Unified Database: System Analysis and Fuel Cycle Option Analysis... Journal September, 2017
Development of Streamlined Nuclear Safety Analyses for Used Nuclear Fuel Applications Journal September, 2017
Summary of Investigations on Technical Feasibility of Direct Disposal of Dual-Purpose Canisters... ORNL Report September, 2017
SFCOMPO-2.0: An OECD NEA Database of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, and Operating Data Journal August, 2017
Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts... Journal August, 2017
