T. M. Rosseel National Lead, Materials Research, Light Water Reactor Sustainability Program Contact 865.574.5384 | ROSSEELTM@ORNL.GOV All Publications Report on Retrieval of the Reactor Pressure Vessel A-60 Surveillance Capsule from Palisades Nuclear Generating Station 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 LIGHT WATER REACTOR SUSTAINABILITY PROGRAM MATERIALS RESEARCH PATHWAY FY 23 TECHNICAL PROGRAM PLAN 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... Life Beyond 80: Can Concrete Degradation Synergistic Modes Become Showstoppers for Light Water Reactors?... Assessment of Neutron Irradiation Damage in Aggregates The Complexity and Challenges of Irradiation-Induced Phase Instability Phenomenon in Nuclear Power Plant Components 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 Ultra-high gamma irradiation of calcium silicate hydrates: Impact on mechanical properties, nanostructure, and atomic environments 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 Plant Concrete Aggregates 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... Pagination Current page 1 Page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group
