Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions Journal July, 2017
ORNL Evaluation of Safety Cases for Two Belgian Reactor Pressure Vessels Containing Quasi-Laminar Defects Conference Paper July, 2017
Study of tritium transport in nuclear-grade graphite and molten fluoride salt systems... Conference Paper July, 2017
A Summary of the Department of Energy's Advanced Demonstration and Test Reactor Options Study Journal July, 2017
Unique Challenges for Modeling Defect Dynamics in Concentrated Solid-Solution Alloys Journal July, 2017
USE OF MINI-CT SPECIMENS FOR FRACTURE TOUGHNESS CHARACTERIZATION OF LOW UPPER-SHELF LINDE 80 WELD ... Conference Paper July, 2017
