Xiang (Frank) Chen R&D Staff Contact chenx2@ornl.gov | 865.574.5058 All Publications 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... Fracture Toughness and Fatigue Crack Growth Rate Testing of Baffle-Former Bolts Harvested from a Westinghouse Two-Loop Downfl... 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... 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 Light Water Reactor Sustainability Program Materials Pathway Technical Program Plan... Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels ... 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 Effects of HFIR neutron irradiation on fracture toughness properties of standard and Ni-doped F82H... 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... 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 f... Pagination First page « First Previous page ‹‹ Page 1 Current 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