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Materials Science

D-Index
76
Citations
26805
World Ranking
3224
National Ranking
903

Research.com Recognitions

  • 2011 - Fellow of the Materials Research Society

Overview

Gary S. Was is affiliated with the University of Michigan-Ann Arbor in the United States. Their research primarily focuses on the field of Materials Science, with substantial contributions to Materials Chemistry, Metals and Alloys, Computational Mechanics, Aerospace Engineering, and Mechanical Engineering as subfields of study.

Their work extensively covers several main topics, including:

  • Crystallization and Solubility Studies
  • Nuclear Materials and Properties
  • Fusion materials and technologies
  • X-ray Diffraction in Crystallography
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Ion-surface interactions and analysis
  • Nuclear materials and radiation effects

Gary S. Was has contributed numerous papers to prominent publication venues, most frequently appearing in:

  • The Cambridge Structural Database (42 publications)
  • Journal of Nuclear Materials (23 publications)
  • Corrosion Science (5 publications)
  • SSRN Electronic Journal (3 publications)
  • Acta Materialia (2 publications)

Some recent publications by Gary S. Was include:

  • "Perspectives on multiscale modelling and experiments to accelerate materials development for fusion" (2021, Journal of Nuclear Materials)
  • "Predicting structural material degradation in advanced nuclear reactors with ion irradiation" (2021, Scientific Reports)
  • "Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments" (2020, Acta Materialia)
  • "Synergies between H, He and radiation damage in dual and triple ion irradiation of candidate fusion blanket materials" (2022, Journal of Nuclear Materials)
  • "Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water" (2020, Journal of Nuclear Materials)

Frequent co-authors in their research include:

  • Kai Sun
  • Hunter B. Tisdale
  • Gregory Morrison
  • Hans-Conrad zur Loye
  • Theodore M. Besmann

Gary S. Was received the award of Fellow of the Materials Research Society in 2011. This recognition is part of their professional profile within the materials science community.

Best Publications

  • Materials Challenges in Nuclear Energy

    Steven J Zinkle;Gary Was

  • Fundamentals of Radiation Materials Science : Metals and Alloys

    Gary Steven Was

  • On the use of SRIM for computing radiation damage exposure

    Roger E. Stoller;Mychailo B. Toloczko;Gary S. Was;Alicia G. Certain

  • Fundamentals of radiation materials science

    Gary S. Was

  • The relationship between hardness and yield stress in irradiated austenitic and ferritic steels

    Jeremy T. Busby;Mark C. Hash;Gary S. Was

  • Corrosion and stress corrosion cracking in supercritical water

    G.S. Was;P. Ampornrat;G. Gupta;S. Teysseyre

  • Radiation-Induced Material Changes and Susceptibility to Intergranular Failure of Light-Water-Reactor Core Internals

    S.M Bruemmer;E.P Simonen;P.M Scott;P.L Andresen

  • Emulation of neutron irradiation effects with protons: validation of principle

    G.S Was;J.T Busby;T Allen;E.A Kenik

  • Deformation and fracture in microlaminates

    G.S Was;T Foecke

  • Emulation of reactor irradiation damage using ion beams

    G.S. Was;Z. Jiao;E. Getto;K. Sun

  • Materials for future nuclear energy systems

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

  • Challenges to the use of ion irradiation for emulating reactor irradiation

    Gary S. Was

  • Ion irradiation-induced phase transformation of pyrochlore and zirconolite

    S.X Wang;L.M Wang;R.C Ewing;G.S Was

  • Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water

    Pantip Ampornrat;Gary S. Was

  • Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems

    Stephen M. Bruemmer;Gary S. Was

  • Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels

    Z. Jiao;G.S. Was

  • Zirconium alloys for supercritical water reactor applications: Challenges and possibilities

    Arthur T. Motta;Aylin Yilmazbayhan;Marcelo J. Gomes da Silva;Robert J. Comstock

  • Microstructural evolution of proton irradiated T91

    G. Gupta;Z. Jiao;A.N. Ham;J.T. Busby

  • The Role of grain boundary misorientation in intergranular cracking of Ni-16Cr-9Fe in 360 °C argon and high-Purity water

    Douglas C. Crawford;Gary S. Was

  • On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys

    T.R. Allen;J.T. Busby;G.S. Was;E.A. Kenik

  • Effects of irradiation on intergranular stress corrosion cracking

    Gary S. Was;Stephen M. Bruemmer

Frequent Co-Authors

Todd R. Allen
Todd R. Allen University of Michigan–Ann Arbor
Kai Sun
Kai Sun University of Tennessee at Knoxville
Ian M. Robertson
Ian M. Robertson University of Wisconsin–Madison
Brian D. Wirth
Brian D. Wirth University of Tennessee at Knoxville
Lumin Wang
Lumin Wang University of Michigan–Ann Arbor
Diana Farkas
Diana Farkas Virginia Tech
Arthur T. Motta
Arthur T. Motta Pennsylvania State University
Lizhen Tan
Lizhen Tan Oak Ridge National Laboratory
Stuart A. Maloy
Stuart A. Maloy Pacific Northwest National Laboratory
Steven J. Zinkle
Steven J. Zinkle University of Tennessee at Knoxville

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