Tim G Lach R&D Scientist Contact 865.341.0581 | lachtg@ornl.gov All Publications Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides Dynamic substrate reactions during room temperature heavy ion irradiation of CoCrCuFeNi high entropy alloy thin films Characterization of radiation damage in 3D printed SiC Evolution of the role of molybdenum in duplex stainless steels during thermal aging: From enhancing spinodal decomposition to forming heterogeneous precipitates Correlative STEM-APT characterization of radiation-induced segregation and precipitation of in-service BWR 304 stainless steel Post-Irradiation Examination of 3D-Printed SiC Precipitation-site competition in duplex stainless steels: Cu clusters vs spinodal decomposition interfaces as nucleation sites during thermal aging Characterization of the Microstructure of Yttrium Hydride under Proton Irradiation Understanding and Removing FIB Artifacts in Metallic TEM Samples Using Flash Electropolishing Complexity of segregation behavior at localized deformation sites formed while in service in a 316 stainless steel baffle-former bolt NSUF BOILER Pre-Irradiation Characterization and High Flux Isotope Reactor Experiment Design Report on the Integration of Experimental and Modeling Data for Initial Equivalence Study of Microstructural Evolution in Irradiated LPBF 316SS In-service Oxidation and IASCC in High Fluence Baffle-Former Bolts Retrieved from a Westinghouse PWR... Thermomechanical Processing for Improved Mechanical Properties of HT9 Steels Characteristics of oxide-dispersion strengthened alloys produced by high-temperature severe deformation A macro-micro approach for identifying crystal plasticity parameters for necking and failure in nickel-based alloy haynes 282 Crystal plasticity modeling and analysis for the transition from intergranular to transgranular failure in nickel-based alloy Inconel 740H at elevated temperature Recent progress in analysis of strain-induced phenomena in irradiated metallic materials and advanced alloys using SEM-EBSD in-situ tensile testing Impact of nano-scale cavities on hydrogen storage and retention in yttrium hydride... Deformation and Fracture Behavior of Additively Manufactured 316L Stainless Steel... Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors Microstructural Characterizations of Two High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-loop Downflow Type PWR Multimodal Characterization of Stored Energy and Gas-Filled Cavities in FCC Alloys Irradiated with Spallation Neutrons and High-Energy Protons Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components Predicting the creep-rupture lifetime of a cast austenitic stainless steel using Larson-Miller and Wilshire parametric approaches Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Curriculum Vitae Google Scholar ORCID LinkedIn Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Nuclear Energy Materials Microanalysis