Xiang (Frank) Chen R&D Staff Contact chenx2@ornl.gov | 865.574.5058 All Publications Post-irradiation Examination Plan for the ORNL and University of California Santa Barbara Assessment of the UCSB ATR-2 Irradi... 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... 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... Reanalysis of Cost and Moist Air Oxidation Performance for CF8C-Plus and Other Alloys for AUSC Applications... Precipitation behavior near shrinkage porosity in a large sand casting of Haynes 282 alloy... 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 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... Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature... 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... PHENIX U.S.-Japan Collaboration Investigation of Thermal and Mechanical Properties of Thermal Neutron–Shielded Irradiated T... Mechanical properties and microstructure characterization of Eurofer97 steel variants in EUROfusion program... 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