Annabelle G Le Coq Associate Technical Staff Member Contact lecoqag@ornl.gov | 865.574.0637 All Publications AMMT FY23 HFIR Irradiation Test Matrix – Supported by the Design of a Miniature Bend Bar Irradiation Vehicle... UCO TRISO Minifuel FY23 NSUF-Kairos Power Post-Irradiation Examination Status Report... Irradiation Testing of Fully Ceramic Microencapsulated (FCM) Fuel Compacts in the High Flux Isotope Reactor... Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron Irradiation–FY23 Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes... Post-Irradiation Examination of Yttrium Hydride Specimens at Oak Ridge National Laboratory... Sensitivity Analysis of TRISO Fuel Configuration in a MiniFuel Irradiation Experiment... Report on Evolution of Inconel 718 Following HFIR Irradiation Separate Effects Testing of TRISO Fuel Particles using the MiniFuel Irradiation Vehicle... TRISO Fuel Performance Pre-test Predictions of HFIR MiniFuel High Power Irradiation... Status Report on Irradiation of MiniFuel Targets bearing TRISO Fuel Compacts... MiniFuel Experimental Capability at Oak Ridge National Laboratory... In Situ Synchrotron Radiation Diffraction Study of Neutron-Irradiated Yttrium Hydrides During Thermal Treatments... Characterization of radiation damage in 3D printed SiC... Irradiation Testing of Silicon Carbide Joint Specimens in the High Flux Isotope Reactor... Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation - FY 2021... Assembly of MiniFuel Targets for Irradiation of U-Mo Fuel Specimens in the High Flux Isotope Reactor... Demonstration of Novel Post-Irradiation Examination Capabilities on MiniFuel Disk Specimens... Assembly of MiniFuel Targets for Irradiation of TRISO Fuel Compacts in the High Flux Isotope Reactor... Current Status of HFIR Irradiation Testing Supporting the Transformational Challenge Reactor... Analysis and Design for Irradiation of High Power TRISO Fuel Compact Specimens in HFIR... Handbook on the Material Properties of Yttrium Hydride for High Temperature Moderator Applications... Mechanical and Thermophysical Properties of 3D-Printed SiC before and after Neutron Irradiation – FY 2021... Irradiation stability and thermomechanical properties of 3D-printed SiC... Pagination Current page 1 Page 2 Next page ›› Last page Last » Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group
