G
Gary S. Was
Researcher at University of Michigan
Publications - 487
Citations - 17725
Gary S. Was is an academic researcher from University of Michigan. The author has contributed to research in topics: Grain boundary & Stress corrosion cracking. The author has an hindex of 56, co-authored 474 publications receiving 14795 citations. Previous affiliations of Gary S. Was include Massachusetts Institute of Technology.
Papers
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Journal ArticleDOI
Oxide-Induced Initiation of Stress Corrosion Cracking in Irradiated Stainless Steel
TL;DR: Stainless steel samples were irradiated with protons at 400°C and strained in 288°C water to examine the role of oxide particles in the irradiation-assisted stress corrosion cracking as discussed by the authors.
Journal ArticleDOI
The mechanism of Zr and Hf in reducing radiation-induced segregation in 316 stainless steel
TL;DR: In this paper, either Zr or Hf was added to 316-type stainless steel, at levels between 0.05 and 0.37 at. pct. Despite similar sizes, first-principles calculations using the Vienna Ab Initio Simulation Package (VASP) demonstrate that solute-vacancy binding for Zr is 1.05 eV vs 0.69 eV for Hf.
Book ChapterDOI
The Influence of Pre-Irradiation Heat Treatments on Thermal Non-Equilibrium and Radiation-Induced Segregation Behavior in Model Austenitic Stainless Steel Alloys
TL;DR: In this paper, the effect of pre-irradiation heat treatments on thermal non-equilibrium grain boundary segregation (TNES) and subsequent radiation-induced grain boundary separation (RIS) is studied in a series of model austenitic stainless steels.
Journal ArticleDOI
Modeling the Effects of Oversize Solute Additions on Radiation-Induced Segregation in Austenitic Stainless Steels
TL;DR: In this paper, the Modified Inverse Kirkendall (MIK) model for RIS in stainless steels was adapted to include the effects of defect trapping, which is expected to be caused by oversized solutes, on RIS.
Book ChapterDOI
Irradiation assisted corrosion and stress corrosion cracking (IAC/IASCC) in nuclear reactor systems and components
Gary S. Was,Peter L. Andresen +1 more
TL;DR: In this paper, the effects of irradiation on the alloy and on water chemistry and their roles in accelerating corrosion and SCC in the in-reactor were discussed. But the authors focused on the effect of radiation on alloy microstructure and water chemistry.