Steven J Zinkle Governor’s Chair for Nuclear Materials Contact ZINKLESJ@ORNL.GOV All Publications Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy Evaluation of the Corrosion Kinetics of SiC with and without Mitigation Coatings in LWR Chemistries... Stability of a model Fe-14Cr nanostructured ferritic alloy after long-term thermal creep Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration Ionizing vs collisional radiation damage in materials: Separated, competing, and synergistic effects in Ti3SiC2 Characterization of the helicon plasma flux to the target of Proto-MPEX Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder Nano-scale microstructure damage by neutron irradiations in a novel Boron-11 enriched TiB2 ultra-high temperature ceramic Post irradiation examination of nanoprecipitate stability and α′ precipitation in an oxide dispersion strengthened Fe-12Cr... Helium induced microstructure damage, nano-scale grain formation and helium retention behaviour of ZrC Primary Radiation Damage: A Review of Current Understanding and Models Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys Irradiation responses and defect behavior of single-phase concentrated solid solution alloys Development of novel Cu-Cr-Nb-Zr alloys with the aid of computational thermodynamics Improving atomic displacement and replacement calculations with physically realistic damage models Effects of temperature on the irradiation responses of Al 0.1 CoCrFeNi high entropy alloy JNM - Phase stability, swelling, microstructure and strength of Ti3SiC¬2-TiC ceramics after low dose neutron irradiation... Microstructural Stability and Mechanical Behavior of FeNiMnCr High Entropy Alloy under Ion Irradiation Scripta - Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2-Ti5Al2C3 materials... High temperature ion irradiation effects in MAX phase ceramics EFFECTS OF ION IRRADIATION ON Zr52.5Cu17.9Ni14.6Al10Ti5 (BAM-11) BULK METALLIC GLASS Evaluation of high strength, high conductivity CuNiBe alloys for fusion energy applications... Accident Tolerant Fuels for LWRs: A Perspective... Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding... Multimodal Options for Materials Research to Advance the Basis for Fusion Energy in the ITER Era ... Pagination First page « First Previous page ‹â¶Ä¹ … Page 2 Current page 3 Page 4 … Next page ›â¶Äº Last page Last » Organizations Physical Sciences Directorate Materials Science and Technology Division
