Wei Tang Sr. Research Staff Contact TANGW@ORNL.GOV All Publications Advanced neutron absorber Ni-Cr-Mo-Gd alloys seawater corrosion mechanism and susceptibility study... Study of Mechanical Properties, Microstructure, and Residual Stresses of AISI 304/304L Stainless Steel Submerged Arc Weld for... Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium... Development of Surface Treatment Solutions for Stamping Tools Fabricated via Additive Manufacturing Defect Recognition for Eddy Current Testing of Spent Nuclear Fuel Canister using Convolutional Neural Network Comprehensive Characterization of Helium-Induced Degradation of the Friction Stir Weld on Neutron-Irradiated 304L Stainless Steel Mechanical responses of 316L stainless steel printed by wire arc additive manufacturing with different thermal histories ADDITIVE MANUFACTURING AND REGULATORY TESTING OF CANISTERS FOR SPENT NUCLEAR FUEL MANAGEMENT Effect of chromium on corrosion resistance of Ni-Cr-Mo-Gd alloys in seawater Temperature-Dependent Thermal and Mechanical Properties of a Wire Arc Additively Manufactured Low Transformation Temperature Steel 316L Stainless Steel Wire Arc Additive Manufacturing and Characterization for Potential SNF Canister Production Friction Stir Welding – an Advanced Approach to Repair Nuclear Power Plant Components Microstructure and mechanical performance of the Friction Stir Welds performed on neutron-irradiated steel with helium Neutron diffraction illustrates residual stress behavior of welded alloys used as radioactive confinement boundary... Produce ZrH Moderator Material A Versatile Remediation Module for Remote Repair of Spent Nuclear Fuel and High-Level Waste Storage Containers REAL-TIME CANISTER WELDING HEALTH MONITORING AND PREDICTION SYSTEM FOR SPENT FUEL DRY STORAGE Stability fo zirconium hydride Welding Process Development for Spent Nuclear Fuel Canister Repair FRICTION STIR WELDING AND PRELIMINARY CHARACTERIZATION OF IRRADIATED 304 STAINLESS STEEL Neutron Residual Stress Mapping of Repaired Spent Nuclear Fuel Welded Stainless-Steel Canisters Complete Report on Development of Weld Repair Technology ADVANCED WELDING TECHNOLOGY DEVELOPMENT FOR NUCLEAR REACTOR REPAIR Evaluating the Potential for Remote In-Process Monitoring of Tool Wear in Friction Stir Welding of Stainless Steel Effects of thread interruptions on tool pins in friction stir welding of AA6061 Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links Google Scholar ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials Structure and Processing Science Section Materials for Advanced Manufacturing Group
