Elena Tajuelo Rodriguez R&D Staff Member Contact 865.241.3874 | tajuelorodre@ornl.gov All Publications Influence of Dissolved Iron in Solution on MgO Hydroxylation and Carbonation... Silicon ion radiation as a viable surrogate for emulating neutron radiation damage in silicates Effects of Neutron Irradiation on the Bond Strength of Steel Embedded in Concrete Reconstruction of 3D Concrete Microstructures Combining High-Resolution Characterization and Convolutional Neural Network for Image Segmentation Radiation-induced alteration of sandstone concrete aggregate 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 LIGHT WATER REACTOR SUSTAINABILITY PROGRAM MATERIALS RESEARCH PATHWAY TECHNICAL PROGRAM PLAN Radiation-induced Alteration of Meta-chert FFT-based model for irradiated aggregate microstructures in concrete Assessment of Neutron Irradiation Damage in Aggregates LWR Aging Management for Life Beyond 80 A Novel Approach to Simulate Realistic Concrete Microstructures under Irradiation Simulation of radiation damage via alpha decay in BFS:PC grouts using 4He2+ ion acceleration Multi-Modal Characterization of Aggregates in Concrete via EDS and Raman imaging Life Beyond 80: Can Concrete Degradation Synergistic Modes Become Showstoppers for Light Water Reactors?... Ultra-high gamma irradiation of calcium silicate hydrates: Impact on mechanical properties, nanostructure, and atomic environments Assessment of San Onofre Concrete Susceptibility Against Irradiation Damage Light Water Reactor Sustainability Program Materials Pathway Technical Program Plan Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC MOSAIC: An Effective FFT-based Numerical Method to Assess Aging Properties of Concrete Microstructural characterization and assessment of mechanical properties of concrete based on combined elemental analysis techniques and Fast-Fourier transform-based simulations Examination of Gamma-irradiated Calcium Silicate Hydrates. Part II: Mechanical Properties Development and Characterization of 3D-Printed Cementitious Systems for Innovative Nuclear Systems Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Curriculum Vitae ORCID https://www.linkedin.com/posts/oak-ridge-national-laboratory_nuestras-historias… Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Advanced Reactor Engineering and Development Section Nuclear Structures and Construction Group
