Xiang Chen Senior R&D Staff Contact 865.574.5058 | CHENX2@ORNL.GOV All Publications 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 Friction Stir Welding – an Advanced Approach to Repair Nuclear Power Plant Components 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 Mechanical properties of Haynes 282 casting Effect of N2- and CO2-containing shielding gases on composition modification and carbonitride precipitation in wire arc additive manufactured grade 91 steel 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 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 Downflow Type PWR 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 after neutron irradiation 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 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
