A Burnup Credit Approach for Margin Estimation of Loaded Boiling Water Reactor Canisters in UNF-ST&DARDS Conference Paper September, 2017
Evaluation of the neutron induced reactions on 235 U from 2.25 keV up to 30 MeV Conference Paper September, 2017
n+ 235 U resonance parameters and neutron multiplicities in the energy region below 100 eV Conference Paper September, 2017
Validation of tungsten cross sections in the neutron energy region up to 100 keV Conference Paper 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
Analysis of Radiation Transport Due to Activated Coolant in the ITER Neutral Beam Injection Cell Journal July, 2017