Yong Yan Distinguished R & D Staff Scientist Contact YANY@ORNL.GOV All Publications Status of the Fuel Fragment Dispersal Studies at Oak Ridge National Laboratory... Hydrogen embrittlement of Zircaloy-4 fabricated by ultrasonic additive manufacturing FUEL FRAGMENT DISPERSAL DURING A POSTBURST VIBRATION EVENT... DEVELOPMENT OF TRANSIENT FISSION GAS RELEASE CAPABILITIES TO STUDY HIGH BURNUP COMMERCIAL FUEL PERFORMANCE UNDER LOSS OF COOLANT ACCIDENT CONDITIONS Recent High Burnup LOCA Testing at Oak Ridge National Laboratory... Fatigue Testing and Characterization of Pre-hydrided Zircaloy-4 Cladding Tubes Dispersal of high-burnup fuel fragment surrogate particles during and after loss-of-coolant accident tests Raman Spectroscopy of Zirconium Hydride... Sister Rod Destructive Examinations (FY22) Appendix E: Mechanical Testing... High-temperature steam oxidation study of irradiated FeCrAl defueled specimens... SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions BISON validation to in situ cladding burst test and high-burnup LOCA experiments Sister Rod Destructive Examinations (FY22) Appendix E: Mechanical Testing Hydrogen effects on thermal diffusivity and electrical resistivity of zircaloy cladding Hydriding, Oxidation, and Ductility Evaluation of Cr-Coated Zircaloy-4 Tubing BISON Validation to In-Situ Cladding Burst Test and High Burnup LOCA Experiments FY23 Post-LOCA Characterization of Irradiated Fuel - NSUF Award 17-12985 Report summarizing demonstration of thermal conductivity measurement methods for coated zirconium cladding Sister Rod Destructive Examinations (FY21) Appendix E Mechanical Testing Destructive Examination of a FeCrAl-UO2 Irradiation Test POST-TEST EXAMINATIONS OF A LOCA SAMPLE FROM AN IRRADIATED HIGH-BURNUP PWR M5 FUEL ROD Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C High Temperature Steam Oxidation of Irradiated FeCrAl in the Severe Accident Test Station Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Fuel Development Section Nuclear Fuel Element Performance Group
