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.
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Irradiation assisted stress corrosion cracking of controlled purity 304L stainless steels
TL;DR: In this article, the effect of chromium, phosphorus, silicon and sulfur on the stress corrosion cracking of 304L stainless steel in CERT tests in high purity water or argon at 288°C following irradiation with 3.4 MeV protons at 400°C to 1 dpa, has been investigated using ultrahigh purity alloys (UHP) with controlled impurity additions.
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Creep and Intergranular Cracking Behavior of Nickel-Chromium-Iron-Carbon Alloys in 360°C Water
TL;DR: In this article, controlled-purity Ni-x% Cr-9% Fe-y% C alloys at 360°C were tested for intergranular (IG) cracking and time-dependent deformation in high-puri...
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Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments
Stephen Taller,Gary S. Was +1 more
TL;DR: In this article, Cavity and dislocation loop evolution was characterized in dual ion irradiated T91 steel in three separate irradiation campaigns examining single parameter dependencies of temperature, helium co-injection rate, and damage rate.
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A historical perspective on understanding IASCC
Peter L. Andresen,Gary S. Was +1 more
TL;DR: In this article, the effects of radiation assisted stress corrosion cracking (IASCC) in unirradiated materials have been investigated, and the key irradiation contributions have been identified.
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Proton-induced grain boundary segregation in stainless steel
D. L. Damcott,D. L. Damcott,J. M. Cookson,R. D. Carter,J. R. Martin,Michael Atzmon,Gary S. Was +6 more
TL;DR: In this article, a technique was developed which addressed the problem of irradiation assisted stress corrosion cracking of stainless steels in light water reactors using high energy protons to induce grain boundary segregation.