Steven J Zinkle Governor’s Chair for Nuclear Materials Contact zinklesj@ornl.gov | 865.576.5785 All Publications 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 a... 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 ... Evaluation of irradiation facility options for fusion materials research and development... CHALLENGES IN DEVELOPING MATERIALS FOR FUSION TECHNOLOGY–PAST, PRESENT AND FUTURE... Advanced Oxidation Resistant Iron Alloys as LWR Fuel Cladding... Materials Challenges in Nuclear Energy... Multimodal Options for Materials Research to Advance the Basis for Fusion Energy in the ITER Era... Pagination First page « First Previous page ‹‹ … Page 2 Current page 3 Page 4 … Next page ›› Last page Last » Organizations Physical Sciences Directorate Materials Science and Technology Division