Steven J Zinkle Governor’s Chair for Nuclear Materials Contact ZINKLESJ@ORNL.GOV All Publications Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions Reconfiguration of an Electrothermal-Arc Plasma Source for In Situ PMI Studies RF sheath induced sputtering on Proto-MPEX part 2: Impurity transport modeling and experimental comparison Perspectives on multiscale modelling and experiments to accelerate materials development for fusion RF sheath induced sputtering on Proto-MPEX. I. Sheath equivalent dielectric layer for modeling the RF sheath Bubble formation in helium-implanted nanostructured ferritic alloys at elevated temperatures Tailoring microstructure in sintered Cu-Cr-Nb-Zr alloys for fusion components Characterization of high thermal conductivity fuel surrogates before and after ion irradiation Summary Report on the Refined User Requirements for U.S. Fusion Prototypic Neutron Source Effect of sink strength on coherency loss of precipitates in dilute Cu-base alloys during in situ ion irradiation Development of the materials analysis and particle probe for Proto-MPEX Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys... Interdiffusion of Elements During Ultrasonic Additive Manufacturing An exploratory study on helium mobility in amorphous and crystallized bulk metallic glasses Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys... Hydrothermal corrosion behavior of CVD SiC in high temperature water Cavity Swelling in Irradiated Materials The effects of neutron and ionizing irradiation on the aqueous corrosion of SiC Effects of irradiation spectrum on the microstructural and mechanical properties of bulk metallic glasses The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys... Structural damage and phase stability of Al0.3CoCrFeNi high entropy alloy under high temperature ion irradiation Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC Contrasting roles of Laves_Cr2Nb precipitates on the creep properties of novel CuCrNbZr alloys... Modern nanostructured ferritic alloys: A compelling and viable choice for sodium fast reactor fuel cladding applications Investigation of the mechanical and microstructural evolution of a Cu based bulk metallic glass during ion irradiation... Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 … Next page ›â¶Äº Last page Last » Organizations Physical Sciences Directorate Materials Science and Technology Division
