Xiang Chen R&D Staff Contact 865.574.5058 | CHENX2@ORNL.GOV All Publications Specimen Size and Geometry Effects on the Master Curve Fracture Toughness Measurements of EUROFER97 and F82H Steels 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 LWR Aging Management for Life Beyond 80 Effect of N2- and CO2-containing shielding gases on composition modification and carbonitride precipitation in wire arc additive manufactured grade 91 steel Mechanical properties of Haynes 282 casting Irradiated stainless steel 347 and irradiated, welded, and hydrogen charged Zircaloy-4 property data for the target solution ... Effects of applied stress and grain size on creep-rupture lifetime prediction for Haynes 282 alloy Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions 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 in-vessel components Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downflow Type PWR LONG-TERM THERMAL AGING EFFECT EVALUATION FOR GRADE 92 AND 316L AT THE LWR RELEVANT TEMPERATURE Post-irradiation Examination Plan for the ORNL and University of California Santa Barbara Assessment of the UCSB ATR-2 Irradi... Light Water Reactor Sustainability Program Materials Pathway Technical Program Plan Fracture Toughness Characterization of Generation II FeCrAl Alloys after ~18 dpa Irradiation Mechanical Properties of Additive Manufacturing 316L Stainless Steel Before and After Neutron Irradiation - FY 2021 Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation Long-Term Creep-Rupture Behavior of Alloy Inconel 740/740H Precipitation behavior near shrinkage porosity in a large sand casting of Haynes 282 alloy Reanalysis of Cost and Moist Air Oxidation Performance for CF8C-Plus and Other Alloys for AUSC Applications Properties of a thick-section narrow-gap gas tungsten arc weld of cast Haynes 282 Mechanical Behavior of Additively Manufactured and Wrought 316L Stainless Steels Before and After Neutron Irradiation Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature MICROSTRUCTURE AND STRENGTH OF A THICK-SECTION GAS-TUNGSTEN ARC WELD IN CAST HAYNES® 282® ALLOY Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group
