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
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.
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.
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.
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.
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Recent Developments in Irradiation-Resistant Steels
G.R. Odette;M.J. Alinger;B.D. Wirth.
Annual Review of Materials Research (2008)
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)
Recent progress in understanding reactor pressure vessel steel embrittlement
G. R. Odette;G. E. Lucas.
Radiation Effects and Defects in Solids (1998)
Ferritic/martensitic steels – overview of recent results
R.L. Klueh;D.S. Gelles;S. Jitsukawa;A. Kimura.
Journal of Nuclear Materials (2002)
Embrittlement of nuclear reactor pressure vessels
G. R. Odette;G. E. Lucas.
JOM (2001)
Primary damage formation in bcc iron
R.E. Stoller;G.R. Odette;B.D. Wirth.
Journal of Nuclear Materials (1997)
On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels
G.R. Odette.
Scripta Metallurgica (1983)
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)
Status of reduced activation ferritic/martensitic steel development
N. Baluc;D.S. Gelles;S. Jitsukawa;A. Kimura.
Journal of Nuclear Materials (2007)
Irradiation-tolerant nanostructured ferritic alloys: Transforming helium from a liability to an asset
G. R. Odette;D. T. Hoelzer.
JOM (2010)
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