Jose' Arregui Mena R&D Staff Contact ARREGUIMENJD@ORNL.GOV All Publications Simulation of radiation damage via alpha decay in BFS:PC grouts using 4He2+ ion acceleration A Novel Approach to Simulate Realistic Concrete Microstructures under Irradiation Life Beyond 80: Can Concrete Degradation Synergistic Modes Become Showstoppers for Light Water Reactors?... Anisotropic thermal diffusivity and conductivity in SiC/SiC tubes studied by infrared imaging and X-ray computed tomography Microstructural characterization data of as received IG-110, 2114 and ETU-10 nuclear graphite grades and oxidation characterization data of IG-110 A general synthesis of single atom catalysts with controllable atomic and mesoporous structures Effects of Pore Discovery Rate on the Ultrasonic Properties of Nuclear Graphites Undergoing Oxidation Issue report summarizing non-destructive characterization and performance of SiC/SiC tubes Effect of microstructure and temperature on nuclear graphite oxidation using the 3D Random Pore Model Thermal diffusivity and thermal conductivity of SiC composite tubes: the effects of microstructure and irradiation The distribution and selective decontamination of carbon-14 from nuclear graphite In-situ X-ray Computed Tomography Analysis of Fracture Mechanisms in Ultrasonic Additively Manufactured Al-6061 Alloy... Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC Probing basal planes and edge sites in polygranular nuclear graphite by gas adsorption: Estimation of active surface area Microstructural characterization of neutron irradiated mineral concrete aggregates Observations of crystal strains in filler and QI particles through TEM examination – Effect of processing and grain size... Recent advances on microstructural characterization and modeling of nuclear graphite Characterization of PyC/SiC interfaces with FIB-SEM tomography... MOSAIC: An Effective FFT-based Numerical Method to Assess Aging Properties of Concrete Electron tomography of unirradiated and irradiated nuclear graphite Microstructural characterization and assessment of mechanical properties of concrete based on combined elemental analysis techniques and Fast-Fourier transform-based simulations Protection of graphite from salt and gas permeation in molten salt reactors Protection of graphite from salt and gas permeation in molten salt reactors Heavy metals and trace elements in the groundwater in El Paso, Texas Development of a Modeling Approach to Describe Thermal Conductivity of Prototypic SiC-SiC tubes for LWR Fuel Cladding Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Page 3 Next page ›› Last page Last » Key Links Google Scholar ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Nuclear Energy Materials Microanalysis
