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Corrosion of similar and dissimilar metal crevices in the engineered barrier system of a potential nuclear waste repository
Authors:X. He  D.S. Dunn
Affiliation:a Center for Nuclear Waste Regulatory Analyses, San Antonio, TX, USA
b Southwest Research Institute®, San Antonio, TX, USA
c U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC, USA
Abstract:Crevice corrosion is considered possible if the corrosion potential (Ecorr) exceeds the repassivation potential for crevice corrosion (Ercrev). In this study, potentiodynamic polarization and potentiostatic hold were used to determine the Ercrev of similar and dissimilar metal crevices in the engineered barrier system of the potential Yucca Mountain repository in 0.5 M NaCl, 4 M NaCl, and 4 M MgCl2 solutions at 95 °C. The results were compared with data previously obtained using crevices formed between Alloy 22 and polytetrafluoroethylene. It was observed that, except for Type 316L stainless steel, all other metal-to-metal crevices were less susceptible to crevice corrosion than the corresponding metal-to-polytetrafluoroethylene crevices. Measurements of galvanic coupling were used to evaluate the crevice corrosion propagation behavior in 5 M NaCl solution at 95 °C. The crevice specimens were coupled to either an Alloy 22 or a Titanium Grade 7 plate using metal or polytetrafluoroethylene crevice washers. Crevice corrosion of Type 316L stainless steel propagated without repassivation. For all the tests using a polytetrafluoroethylene crevice washer, crevice corrosion of Alloy 22 was initiated at open circuit potential by the addition of CuCl2 as an oxidant, whereas no crevice corrosion of Alloy 22 was initiated for all the tests using Alloy 22 or Titanium Grade 7 metals as crevice washer. However, crevice corrosion propagation was found to be very limited under such test conditions.
Keywords:Alloy 22   Crevice corrosion   Crevice corrosion repassivation potential   Titanium Grade 7   316L stainless steel
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