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Electrochemical corrosion of electrodes in a simulated nuclear waste glass melt

机译:模拟核废玻璃熔体中电极的电化学腐蚀

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摘要

Corrosion of potential candidate electrode materials, molybdenum and tantalum, in a simulated nuclear waste glass melt was investigated using electrochemical (dc-powered) and non-powered tests. Electrochemical corrosion data showed that tantalum was more corrosion-resistant than molybdenum in this melt. Tantalum also showed passivation. The non-powered test data showed that tantalum corroded more than molybdenum. This was attributed to penetration of protective passivation layer at the tantalum-glass interface by the glass melt. Microstructural features and chemistry across selected electrode-glass interfacial regions supported these results.
机译:使用电化学测试(直流供电)和非供电测试研究了模拟核废玻璃熔体中潜在候选电极材料钼和钽的腐蚀。电化学腐蚀数据表明,在该熔体中,钽比钼更具抗腐蚀性。钽也表现出钝化作用。无动力测试数据表明,钽的腐蚀程度比钼大。这归因于玻璃熔体在钽-玻璃界面处保护钝化层的渗透。跨选定的电极-玻璃界面区域的微观结构特征和化学性质支持了这些结果。

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