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Title: Near-field corrosion interactions between glass and corrosion resistant alloys

Journal Article · · npj Materials Degradation
ORCiD logo [1]; ORCiD logo [2]; ORCiD logo [3];  [3];  [3];  [3];  [1];  [4];  [4]; ORCiD logo [1]
  1. The Ohio State Univ., Columbus, OH (United States). Dept. of Materials Science and Engineering
  2. Univ. de Montpellier, Marcoule (France)
  3. Pennsylvania State Univ., University Park, PA (United States). Dept. of Chemical Engineering and Materials Research Inst.
  4. Pacific Northwest National Lab. (PNNL), Richland, WA (United States). Energy and Environment Directorate

This study explores the corrosion interactions between model nuclear waste glass materials and corrosion resistant alloys, under accelerated conditions that simulate the near field of a nuclear waste repository. The interactions between the corrosion of stainless steel (SS) 316, alloy G30, or alloy 625, and international simple glass or soda-lime silica glass are systematically studied. The dissimilar materials were exposed in close proximity to each other in different electrolytes at 90 °C. After exposure, the glass surface exposed near metals showed different regimes of corrosion, with distinct surface morphologies and chemistries that were likely affected by the local environment created by the localized corrosion of metals. Surface and solution analyses showed that the corrosion rate of glass was enhanced by the presence of metals. Infrared spectroscopy data suggested the local build-up of stresses in the contact area of glass, which may lead to the mechanical instability of the glass alteration layer. On the other hand, the effect of glass on metal corrosion is strongly dependent on the leaching solution. In electrolytes containing abundant aggressive anions such as Cl, glass seems to suppress the localized corrosion of SS by the precipitation of a Si-rich surface film that protects the SS substrate from solutions. However, in less aggressive electrolytes, the corrosion rate of SS was increased by the presence of glass corrosion products. Overall, our study showed that the hidden and localized damage on glass in contact with metals may enhance the release rate of glass components compared to typical uniform glass corrosion.

Research Organization:
Energy Frontier Research Centers (EFRC) (United States). Center for Performance and Design of Nuclear Waste Forms and Containers (WastePD); The Ohio State Univ., Columbus, OH (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Basic Energy Sciences (BES)
Grant/Contract Number:
SC0016584
OSTI ID:
1666385
Journal Information:
npj Materials Degradation, Vol. 4, Issue 1; ISSN 2397-2106
Publisher:
SpringerCopyright Statement
Country of Publication:
United States
Language:
English

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