2013 - Fellow of American Physical Society (APS) Citation For significant contributions to the fundamental understanding of radiation effects in metallic and ceramic materials
2013 - Fellow of the Materials Research Society
2012 - Member of the National Academy of Engineering For advancing understanding of radiation damage in metallic and ceramic components.
2009 - Fellow of the American Association for the Advancement of Science (AAAS)
His primary scientific interests are in Irradiation, Metallurgy, Fusion power, Microstructure and Nuclear engineering. His Irradiation research is multidisciplinary, incorporating elements of Transmission electron microscopy, Ionization, Atomic physics, Analytical chemistry and Composite material. His Metallurgy study is mostly concerned with Creep, Alloy, Ceramic, Zirconium alloy and Austenitic stainless steel.
The Fusion power study combines topics in areas such as Vanadium, Compatibility and Structural material. His Microstructure course of study focuses on Dislocation and Deformation. His Nuclear engineering study combines topics in areas such as Neutron, Neutron source, Silicon carbide and Blanket.
His primary areas of investigation include Irradiation, Metallurgy, Microstructure, Analytical chemistry and Composite material. Steven J. Zinkle has researched Irradiation in several fields, including Nuclear chemistry, Crystallography, Dislocation, Transmission electron microscopy and Copper. His research on Metallurgy often connects related areas such as Fusion power.
His Fusion power study which covers Divertor that intersects with Nuclear engineering. His Microstructure research is multidisciplinary, relying on both Deformation, Swelling, Spinel and Crystallite. The study incorporates disciplines such as Amorphous solid, Hardening, Atmospheric temperature range, Vacancy defect and Fluence in addition to Analytical chemistry.
The scientist’s investigation covers issues in Irradiation, Microstructure, Analytical chemistry, Alloy and Composite material. His biological study spans a wide range of topics, including Void, Hardening, Transmission electron microscopy, Dislocation and Amorphous metal. His Microstructure study is concerned with Metallurgy in general.
The concepts of his Analytical chemistry study are interwoven with issues in Vacancy defect and Fluence. His Alloy research is multidisciplinary, incorporating perspectives in Thermodynamics and Austenite. As a member of one scientific family, Steven J. Zinkle mostly works in the field of Composite material, focusing on Annealing and, on occasion, Nuclear reaction analysis and Helium.
His main research concerns Irradiation, Microstructure, Alloy, Transmission electron microscopy and Annealing. Steven J. Zinkle has included themes like Atom probe, Void, Atomic physics and Analytical chemistry in his Irradiation study. Microstructure is the subject of his research, which falls under Metallurgy.
His Alloy research incorporates themes from Composite number, Diffraction, Thermodynamics and Grain Boundary Sliding. The various areas that Steven J. Zinkle examines in his Transmission electron microscopy study include Scanning electron microscope and Dislocation. Steven J. Zinkle interconnects Hardening, Composite material, Nanoindentation and Amorphous metal in the investigation of issues within Annealing.
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Materials Challenges in Nuclear Energy
Steven J Zinkle;Gary Was.
Acta Materialia (2013)
Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium
W. J. Weber;R. C. Ewing;C. R. A. Catlow;T. Diaz de la Rubia.
Journal of Materials Research (1998)
Structural materials for fission & fusion energy
Steven J. Zinkle;Jeremy T. Busby.
Materials Today (2009)
Accident tolerant fuels for LWRs: A perspective
Steven J Zinkle;Steven J Zinkle;Kurt A Terrani;Jess C Gehin;Larry J Ott.
Journal of Nuclear Materials (2014)
Operating temperature windows for fusion reactor structural materials
S.J Zinkle;N.M Ghoniem.
Fusion Engineering and Design (2000)
Defect production in ceramics
S.J. Zinkle;C. Kinoshita.
Journal of Nuclear Materials (1997)
Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding
Kurt A Terrani;Steven J Zinkle;Lance Lewis Snead.
Journal of Nuclear Materials (2014)
Radiation effects in ceramics
Linn W. Hobbs;Frank W. Clinard;Steven J. Zinkle;Rodney C. Ewing.
Journal of Nuclear Materials (1994)
On the exploration of innovative concepts for fusion chamber technology
M. A. Abdou;A. Ying;N. Morley.
Fusion Engineering and Design (2001)
Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel
S.J. Zinkle;P.J. Maziasz;R.E. Stoller.
Journal of Nuclear Materials (1993)
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