D-Index & Metrics Best Publications

D-Index & Metrics

Discipline name D-index D-index (Discipline H-index) only includes papers and citation values for an examined discipline in contrast to General H-index which accounts for publications across all disciplines. Citations Publications World Ranking National Ranking
Materials Science D-index 75 Citations 21,369 344 World Ranking 1351 National Ranking 474

Research.com Recognitions

Awards & Achievements

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)

Overview

What is he best known for?

The fields of study he is best known for:

  • Electron
  • Thermodynamics
  • Composite material

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 most cited work include:

  • Materials Challenges in Nuclear Energy (968 citations)
  • Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium (723 citations)
  • Structural materials for fission & fusion energy (554 citations)

What are the main themes of his work throughout his whole career to date?

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.

He most often published in these fields:

  • Irradiation (56.12%)
  • Metallurgy (32.40%)
  • Microstructure (34.44%)

What were the highlights of his more recent work (between 2017-2021)?

  • Irradiation (56.12%)
  • Microstructure (34.44%)
  • Analytical chemistry (26.02%)

In recent papers he was focusing on the following fields of study:

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.

Between 2017 and 2021, his most popular works were:

  • Primary radiation damage: A review of current understanding and models (121 citations)
  • Primary radiation damage: A review of current understanding and models (121 citations)
  • Improving atomic displacement and replacement calculations with physically realistic damage models (107 citations)

In his most recent research, the most cited papers focused on:

  • Electron
  • Thermodynamics
  • Composite material

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.

This overview was generated by a machine learning system which analysed the scientist’s body of work. If you have any feedback, you can contact us here.

Best Publications

Materials Challenges in Nuclear Energy

Steven J Zinkle;Gary Was.
Acta Materialia (2013)

1096 Citations

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)

924 Citations

Structural materials for fission & fusion energy

Steven J. Zinkle;Jeremy T. Busby.
Materials Today (2009)

664 Citations

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)

545 Citations

Operating temperature windows for fusion reactor structural materials

S.J Zinkle;N.M Ghoniem.
Fusion Engineering and Design (2000)

462 Citations

Defect production in ceramics

S.J. Zinkle;C. Kinoshita.
Journal of Nuclear Materials (1997)

427 Citations

Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding

Kurt A Terrani;Steven J Zinkle;Lance Lewis Snead.
Journal of Nuclear Materials (2014)

373 Citations

Radiation effects in ceramics

Linn W. Hobbs;Frank W. Clinard;Steven J. Zinkle;Rodney C. Ewing.
Journal of Nuclear Materials (1994)

344 Citations

On the exploration of innovative concepts for fusion chamber technology

M. A. Abdou;A. Ying;N. Morley.
Fusion Engineering and Design (2001)

337 Citations

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)

299 Citations

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