Xiang Chen Senior R&D Staff Contact 865.574.5058 | CHENX2@ORNL.GOV All Publications MICROSTRUCTURE AND STRENGTH OF A THICK-SECTION GAS-TUNGSTEN ARC WELD IN CAST HAYNES® 282® ALLOY Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H... Post-Irradiation Evaluation of Eurofer97 Fracture Toughness Using Miniature Multinotch Bend Bar Specimens Guidelines for IAEA Small Specimen Test Techniques Master Curve Fracture Toughness Testing CHARACTERIZATION OF NI-BASED ALLOYS FOR ADVANCED ULTRA-SUPERCRITICAL POWER PLANTS Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys Handbook of advanced manufactured material properties from TCR structure builds at ORNL – FY19 Post-Irradiation Examination of High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-Loop Downflow Type PWR Post-Irradiation Examination of High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-Loop Downflow Type PWR Master Curve Fracture Toughness Characterization of Eurofer97 Steel Variants Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated Tungsten Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program Fixture Development for Fracture Toughness Testing of Irradiated RAFM Steels Using Miniature Multi-Notch Bend Bar Specimens Using Automated J-R Curve Analysis Software to Simplify Testing and Save Time... Strain evaluation using a non-contact deformation measurement system in tensile tests of irradiated F82H and 9cr ODS steels... Impact toughness of commercial and model FeCrAl alloys... Master Curve Fracture Toughness Characterization of Eurofer97 Using Miniature Multi-Notch Bend Bar Specimens for Fusion Applications CURRENT STATUS OF THE CHARACTERIZATION OF RPV MATERIALS HARVESTED FROM THE DECOMMISSIONED ZION UNIT 1 NUCLEAR POWER PLANT The Plan for Post-Irradiation Examination of Zion Reactor Pressure Vessel Beltline Materials Application of a Novel DCPD Adjustment Method for the J-R Curve Characterization: A study based on ORNL and ASTM Interlaboratory Results Application of Direct Current Potential Drop for the J-integral vs. Crack Growth Resistance Curve Characterization J-R Curve Determination for Disk-shaped Compact Specimens Based on the Normalization Method and Direct Current Potential Drop... Determining Ductile Fracture Toughness in Metals Effect of Creep and Oxidation on Reduced Creep-Fatigue life of Ni-based Alloy 617 at 850 ºC... Application of Direct Current Potential Drop for Fracture Toughness Measurement... Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 Next page ›› Last page Last » Key Links Google Scholar ORCID LinkedIn 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
