D-Index & Metrics Best Publications

D-Index & Metrics 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.

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
Mechanical and Aerospace Engineering D-index 62 Citations 13,101 215 World Ranking 324 National Ranking 169
Materials Science D-index 62 Citations 13,133 228 World Ranking 3909 National Ranking 1148

Research.com Recognitions

Awards & Achievements

2019 - Fellow of the American Association for the Advancement of Science (AAAS)

2018 - ASM Fellow "For excellence and sustained seminal contributions to measuring, modeling, and managing 

Overview

What is he best known for?

The fields of study he is best known for:

  • Composite material
  • Metallurgy
  • Thermodynamics

His primary areas of study are Metallurgy, Fusion power, Martensite, Embrittlement and Irradiation. His research on Metallurgy often connects related topics like Nuclear transmutation. His studies deal with areas such as Number density, Nuclear engineering, Neutron source, Compatibility and Vanadium as well as Fusion power.

The Martensite study combines topics in areas such as Fracture toughness, Blanket, Neutron irradiation and Structural material. His Embrittlement research includes themes of Chemical physics, Reactor pressure vessel, Hardening, Pressure vessel and Vacancy defect. His study in the fields of Radiation damage under the domain of Irradiation overlaps with other disciplines such as Dumbbell.

His most cited work include:

  • Recent Developments in Irradiation-Resistant Steels (818 citations)
  • On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys (301 citations)
  • Recent progress in understanding reactor pressure vessel steel embrittlement (273 citations)

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

Metallurgy, Irradiation, Composite material, Fracture toughness and Alloy are his primary areas of study. His Metallurgy study frequently links to related topics such as Fusion power. His study in Irradiation is interdisciplinary in nature, drawing from both Hardening, Helium, Analytical chemistry and Embrittlement.

His Embrittlement study combines topics in areas such as Reactor pressure vessel, Pressure vessel, Cascade, Copper and Vacancy defect. His Fracture toughness research incorporates elements of Fracture mechanics, Fracture, Brittleness, Toughness and Cleavage. His studies in Ultimate tensile strength integrate themes in fields like Creep and Strain rate.

He most often published in these fields:

  • Metallurgy (48.26%)
  • Irradiation (33.48%)
  • Composite material (24.35%)

What were the highlights of his more recent work (between 2011-2021)?

  • Irradiation (33.48%)
  • Metallurgy (48.26%)
  • Composite material (24.35%)

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

The scientist’s investigation covers issues in Irradiation, Metallurgy, Composite material, Analytical chemistry and Alloy. His Irradiation research integrates issues from Martensite, Hardening, Embrittlement and Neutron. His Martensite research is multidisciplinary, relying on both Blanket and Neutron irradiation.

The study incorporates disciplines such as Fusion power and Nucleation in addition to Metallurgy. His Analytical chemistry study incorporates themes from Scanning transmission electron microscopy, Atom probe, Transmission electron microscopy, Annealing and Ferrite. His work carried out in the field of Alloy brings together such families of science as Helium, Microstructure, Radiation damage and Dislocation.

Between 2011 and 2021, his most popular works were:

  • Recent progress of R&D activities on reduced activation ferritic/martensitic steels (142 citations)
  • Recent Progress in Developing and Qualifying Nanostructured Ferritic Alloys for Advanced Fission and Fusion Applications (119 citations)
  • Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications (92 citations)

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

  • Composite material
  • Thermodynamics
  • Metallurgy

His main research concerns Metallurgy, Atom probe, Alloy, Oxide and Analytical chemistry. His Metallurgy research integrates issues from Composite material, Fusion power and Nucleation. Thermodynamics, Diffusion and Hardening is closely connected to Precipitation in his research, which is encompassed under the umbrella topic of Alloy.

The concepts of his Analytical chemistry study are interwoven with issues in Indentation hardness, Transmission electron microscopy, Irradiation, Volume fraction and Grain size. G.R. Odette usually deals with Intermetallic and limits it to topics linked to Nuclear reactor and Embrittlement. The various areas that G.R. Odette examines in his Martensite study include Blanket and Neutron irradiation.

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

Recent Developments in Irradiation-Resistant Steels

G.R. Odette;M.J. Alinger;B.D. Wirth.
Annual Review of Materials Research (2008)

1172 Citations

On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys

M.J. Alinger;G.R. Odette;D.T. Hoelzer.
Acta Materialia (2009)

435 Citations

Recent progress in understanding reactor pressure vessel steel embrittlement

G. R. Odette;G. E. Lucas.
Radiation Effects and Defects in Solids (1998)

407 Citations

Ferritic/martensitic steels – overview of recent results

R.L. Klueh;D.S. Gelles;S. Jitsukawa;A. Kimura.
Journal of Nuclear Materials (2002)

392 Citations

Embrittlement of nuclear reactor pressure vessels

G. R. Odette;G. E. Lucas.
JOM (2001)

384 Citations

Primary damage formation in bcc iron

R.E. Stoller;G.R. Odette;B.D. Wirth.
Journal of Nuclear Materials (1997)

343 Citations

On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels

G.R. Odette.
Scripta Metallurgica (1983)

313 Citations

Influence of Particle Dispersions on the High-Temperature Strength of Ferritic Alloys

David T Hoelzer;James Bentley;Mikhail A Sokolov;Michael K Miller.
Journal of Nuclear Materials (2007)

251 Citations

Status of reduced activation ferritic/martensitic steel development

N. Baluc;D.S. Gelles;S. Jitsukawa;A. Kimura.
Journal of Nuclear Materials (2007)

245 Citations

Irradiation-tolerant nanostructured ferritic alloys: Transforming helium from a liability to an asset

G. R. Odette;D. T. Hoelzer.
JOM (2010)

236 Citations

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