World's Best Scientists 2026 revealed!

D-Index & Metrics

Materials Science

D-Index
83
Citations
31266
World Ranking
2324
National Ranking
673

Steven J. Zinkle publication distribution in Materials Science in 2026

The chart shows the distribution of publications by all Research.com ranked scientists in the field of Materials Science in 2026. The highlighted bar marks where Steven J. Zinkle sits on this spectrum.

50–69 publications: 28 scientists 70–89 publications: 152 scientists 90–109 publications: 356 scientists 110–129 publications: 487 scientists 130–149 publications: 723 scientists 150–169 publications: 835 scientists 170–189 publications: 850 scientists 190–209 publications: 891 scientists 210–229 publications: 862 scientists 230–249 publications: 766 scientists 250–269 publications: 726 scientists 270–289 publications: 665 scientists 290–309 publications: 593 scientists 310–329 publications: 537 scientists 330–349 publications: 477 scientists 350–369 publications: 440 scientists 370–389 publications: 356 scientists 390–409 publications: 321 scientists 410–429 publications: 256 scientists 430–449 publications: 246 scientists 450–469 publications: 216 scientists 470–489 publications: 212 scientists 490–509 publications: 174 scientists 510–529 publications: 194 scientists 530–549 publications: 162 scientists 550–569 publications: 131 scientists 570–589 publications: 111 scientists 590–609 publications: 103 scientists 610–629 publications: 99 scientists 630–649 publications: 77 scientists 650–669 publications: 92 scientists 670–689 publications: 56 scientists 690–709 publications: 53 scientists 710–729 publications: 53 scientists 730–749 publications: 38 scientists 750–769 publications: 52 scientists 770–789 publications: 43 scientists 790–809 publications: 38 scientists 810–829 publications: 34 scientists 830–849 publications: 25 scientists 850–869 publications: 18 scientists 870–889 publications: 20 scientists 890–909 publications: 24 scientists 910–929 publications: 27 scientists 930–949 publications: 20 scientists 950–969 publications: 17 scientists 970–989 publications: 10 scientists 990–1,009 publications: 16 scientists 1,010–1,029 publications: 13 scientists 1,030–1,049 publications: 12 scientists 1,050–1,069 publications: 9 scientists 1,070–1,089 publications: 8 scientists 1,090–1,109 publications: 7 scientists 1,110–1,129 publications: 9 scientists 1,130–1,149 publications: 2 scientists 1,150–1,162 publications: 5 scientists 1,163+ publications: 100 scientists
50 publications 1,163+

This scientist: 440 publications — 81st percentile

81% of scientists in this discipline score the same or lower.

The last bar groups every scientist with 1,163 publications or more.

Steven J. Zinkle D-index placement in Materials Science in 2026

The chart shows the D-index (discipline H-index) distribution of Materials Science scientists ranked by Research.com in 2026. The highlighted bar marks where Steven J. Zinkle sits on this spectrum.

40–41 D-Index: 211 scientists 42–43 D-Index: 450 scientists 44–45 D-Index: 612 scientists 46–47 D-Index: 612 scientists 48–49 D-Index: 598 scientists 50–51 D-Index: 657 scientists 52–53 D-Index: 667 scientists 54–55 D-Index: 621 scientists 56–57 D-Index: 597 scientists 58–59 D-Index: 610 scientists 60–61 D-Index: 587 scientists 62–63 D-Index: 606 scientists 64–65 D-Index: 533 scientists 66–67 D-Index: 490 scientists 68–69 D-Index: 469 scientists 70–71 D-Index: 378 scientists 72–73 D-Index: 421 scientists 74–75 D-Index: 359 scientists 76–77 D-Index: 323 scientists 78–79 D-Index: 299 scientists 80–81 D-Index: 230 scientists 82–83 D-Index: 210 scientists 84–85 D-Index: 195 scientists 86–87 D-Index: 203 scientists 88–89 D-Index: 175 scientists 90–91 D-Index: 175 scientists 92–93 D-Index: 142 scientists 94–95 D-Index: 121 scientists 96–97 D-Index: 117 scientists 98–99 D-Index: 107 scientists 100–101 D-Index: 88 scientists 102–103 D-Index: 85 scientists 104–105 D-Index: 68 scientists 106–107 D-Index: 62 scientists 108–109 D-Index: 57 scientists 110–111 D-Index: 45 scientists 112–113 D-Index: 49 scientists 114–115 D-Index: 50 scientists 116–117 D-Index: 34 scientists 118–119 D-Index: 38 scientists 120–121 D-Index: 37 scientists 122–123 D-Index: 29 scientists 124–125 D-Index: 28 scientists 126–127 D-Index: 24 scientists 128–129 D-Index: 33 scientists 130–131 D-Index: 28 scientists 132–133 D-Index: 21 scientists 134–135 D-Index: 20 scientists 136–137 D-Index: 23 scientists 138–139 D-Index: 17 scientists 140–141 D-Index: 12 scientists 142–143 D-Index: 17 scientists 144–145 D-Index: 21 scientists 146–147 D-Index: 13 scientists 148–149 D-Index: 11 scientists 150–151 D-Index: 14 scientists 152–153 D-Index: 13 scientists 154–155 D-Index: 9 scientists 156–157 D-Index: 10 scientists 158–159 D-Index: 7 scientists 160–161 D-Index: 4 scientists 162–163 D-Index: 4 scientists 164 D-Index: 3 scientists 165+ D-Index: 98 scientists
40 D-Index 165+

This scientist: 83 D-Index — 82nd percentile

82% of scientists in this discipline score the same or lower.

The last bar groups every scientist with 165 D-Index or more.

Research.com Recognitions

  • 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.

Best Publications

  • Materials Challenges in Nuclear Energy

    Steven J Zinkle;Gary Was

  • Structural materials for fission & fusion energy

    Steven J. Zinkle;Jeremy T. Busby

  • Accident tolerant fuels for LWRs: A perspective

    Steven J Zinkle;Steven J Zinkle;Kurt A Terrani;Jess C Gehin;Larry J Ott

  • 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

  • Designing Radiation Resistance in Materials for Fusion Energy

    Steven J Zinkle;Lance Lewis Snead

  • Advanced Oxidation Resistant Iron-Based Alloys for LWR Fuel Cladding

    Kurt A Terrani;Steven J Zinkle;Lance Lewis Snead

  • Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation

    N.A.P. Kiran Kumar;C. Li;K.J. Leonard;H. Bei

  • Primary radiation damage: A review of current understanding and models

    Kai Nordlund;Steven J. Zinkle;Steven J. Zinkle;Andrea E. Sand;Fredric Granberg

  • Operating temperature windows for fusion reactor structural materials

    S.J Zinkle;N.M Ghoniem

  • Defect production in ceramics

    S.J. Zinkle;C. Kinoshita

  • On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials

    R.E. Stoller;S.J. Zinkle

  • Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel

    S.J. Zinkle;P.J. Maziasz;R.E. Stoller

  • On the exploration of innovative concepts for fusion chamber technology

    M. A. Abdou;A. Ying;N. Morley

  • Radiation effects in ceramics

    Linn W. Hobbs;Frank W. Clinard;Steven J. Zinkle;Rodney C. Ewing

  • Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences

    L.K Mansur;A.F Rowcliffe;R.K Nanstad;S.J Zinkle

  • Improving atomic displacement and replacement calculations with physically realistic damage models

    Kai Nordlund;Steven J. Zinkle;Steven J. Zinkle;Andrea E. Sand;Fredric Granberg

  • Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations

    S.J. Zinkle;S.J. Zinkle;L.L. Snead

  • High pressure synthesis of a hexagonal close-packed phase of the high-entropy alloy CrMnFeCoNi

    Cameron L. Tracy;Sulgiye Park;Dylan R. Rittman;Steven J. Zinkle

  • Defect accumulation in pure FCC metals in the transient regime: A review

    B.N. Singh;S.J. Zinkle

  • Materials for future nuclear energy systems

    G.S. Was;D. Petti;S. Ukai;S. Zinkle

  • Fusion materials science: Overview of challenges and recent progressa)

    Steven J. Zinkle

  • Vanadium alloys - overview and recent results

    T. Muroga;T. Nagasaka;K. Abe;V.M. Chernov

Frequent Co-Authors

David T. Hoelzer
David T. Hoelzer Oak Ridge National Laboratory
Roger E. Stoller
Roger E. Stoller Oak Ridge National Laboratory
Bachu Narain Singh
Bachu Narain Singh Technical University of Denmark
William J. Weber
William J. Weber University of Tennessee at Knoxville
Nasr M. Ghoniem
Nasr M. Ghoniem University of California, Los Angeles
Hongbin Bei
Hongbin Bei Zhejiang University
Yutai Katoh
Yutai Katoh Oak Ridge National Laboratory
Thak Sang Byun
Thak Sang Byun Oak Ridge National Laboratory
Rodney C. Ewing
Rodney C. Ewing Stanford University

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