T. M. Rosseel National Lead, Materials Research, Light Water Reactor Sustainability Program Contact rosseeltm@ornl.gov | 865.574.5384 All Publications Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium Reconstruction of 3D Concrete Microstructures Combining High-Resolution Characterization and Convolutional Neural Network for Image Segmentation Comprehensive Characterization of Helium-Induced Degradation of the Friction Stir Weld on Neutron-Irradiated 304L Stainless Steel Ultrasonic Assessment of Neutron Irradiated Concrete-Forming Aggregates LWRSP Materials Research Pathway FY 22 Technical Program Plan... Weldability of irradiated Stainless Steel 304 materials harvested from the National Research Universal (NRU) reactor... LIGHT WATER REACTOR SUSTAINABILITY PROGRAM MATERIALS RESEARCH PATHWAY TECHNICAL PROGRAM PLAN FFT-based model for irradiated aggregate microstructures in concrete... Complete the weld campaign on Ni-base irradiated materials using stress improved laser welding including the preliminary weld quality inspections A Novel Approach to Simulate Realistic Concrete Microstructures under Irradiation... Friction Stir Welding – an Advanced Approach to Repair Nuclear Power Plant Components... LWR Aging Management for Life Beyond 80... Microstructural Characterization of the Second High Fluence Baffle-Former Bolt Retrieved from a Westinghouse Two-loop Downflow Type PWR Life Beyond 80: Can Concrete Degradation Synergistic Modes Become Showstoppers for Light Water Reactors?... Assessment of Neutron Irradiation Damage in Aggregates... Ultra-high gamma irradiation of calcium silicate hydrates: Impact on mechanical properties, nanostructure, and atomic environ... Morphology and elemental composition of a new iron-rich ferrite phase in highly irradiated austenitic steel... Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage... Radiation-Induced Changes in Single Crystal Calcite and Dolomite: Mineral Analogues of Light Water Reactor, Nuclear Power Pla... Experimental Evaluation of Deformation and Fracture Mechanisms in Highly Irradiated Austenitic Steels... Microstructure and mechanical performance of the Friction Stir Welds performed on neutron-irradiated steel with helium... Post-irradiation Examination Plan for the ORNL and University of California Santa Barbara Assessment of the UCSB ATR-2 Irradi... Quantification of in-grain lattice gradient in neutron irradiated 304L SS during deformation using insitu EBSD... Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructu... Complexity of deformation mechanism in neutron-irradiated 304L austenitic stainless steel at microstructural scale Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group
