Xiang (Frank) Chen R&D Staff Contact chenx2@ornl.gov | 865.574.5058 All Publications Microstructure and mechanical properties of friction stir weld performed on neutron-irradiated 304L steel with helium Irradiation creep measurement and microstructural analysis of chromium nitride–coated zirconium alloy using pressurized tubes Mechanical Properties of Neutron-Irradiated Zr-Alloy Weldments (Batch #2) Comprehensive Characterization of Helium-Induced Degradation of the Friction Stir Weld on Neutron-Irradiated 304L Stainless Steel Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors Assessment of Different Approaches for Measuring Shear Fracture Appearance in Charpy Tests 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 approa... Replacement of Hydraulic Power Units in the Fracture Mechanics Laboratory of Oak Ridge National Laboratory Influence of fatigue precracking and specimen size on Master Curve fracture toughness measurements of EUROFER97 and F82H steels LWRSP Materials Research Pathway FY 22 Technical Program Plan... LIGHT WATER REACTOR SUSTAINABILITY PROGRAM MATERIALS RESEARCH PATHWAY TECHNICAL PROGRAM PLAN Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys... Second group of irradiation capsules: property data of irradiated welded stainless steel 347 and irradiated, welded, and hydrogen charged Zircaloy-4 for SHINE Specimen Size and Geometry Effects on the Master Curve Fracture Toughness Measurements of EUROFER97 and F82H Steels... 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 Friction Stir Welding – an Advanced Approach to Repair Nuclear Power Plant Components... Mechanical properties of Haynes 282 casting... Effect of N2- and CO2-containing shielding gases on composition modification and carbonitride precipitation in wire arc addit... Effects of applied stress and grain size on creep-rupture lifetime prediction for Haynes 282 alloy... Irradiated stainless steel 347 and irradiated, welded, and hydrogen charged Zircaloy-4 property data for the target solution ... Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant condition... Effect of heterogeneous microstructure on the tensile and creep performances of cast Haynes 282 alloy The status of the Japanese material properties handbook and the challenge to facilitate structural design criteria for DEMO i... Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links Google Scholar ORCID LinkedIn DOE-NE Light Water Reactor Sustainability Program - Materials Research Pathway Automated Normalization Software for J-R Curve Analysis Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group