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Corrosion studies in support of a medium-power lead-alloy-cooled reactor

机译：支持中功率铅合金冷却反应堆的腐蚀研究

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摘要

The performance of structural materials in lead or lead-bismuth eutectic (LBE) systems is evaluated. The materials evaluated included refractory metals (W, Mo, and Ta), several U.S. steels [austenitic steel (316L), carbon steels (F-22, Fe-Si), ferritic/martensitic steels (HT-9 and 410)], and several experimental Fe-Si-Cr alloys that were expected to demonstrate corrosion resistance. The materials were exposed in either an LBE rotating electrode or a dynamic corrosion cell for periods from 100 to 1000 h at temperatures of 400, 500, 600, and 700degreesC, depending on material and exposure location. Weight change and optical scanning electron microscopy or X-ray analysis of the specimen were used to characterize oxide film thickness, corrosion depth, microstructure, and composition changes. The results of corrosion tests validate the excellent resistance of refractory metals (W, Ta, and Mo) to LBE corrosion. The tests conducted with stainless steels (410, 316L, and HT-9) produced mass transfer of elements (e.g., Ni and Cr) into the LBE, resulting in degradation of the material. With Fe-Si alloys a Si-rich layer (as SiO2) is formed on the surface during exposure to LBE from the selective dissolution of Fe.
机译：评估了铅或铅铋共晶（LBE）系统中结构材料的性能。评估的材料包括难熔金属（W，Mo和Ta），几种美国钢[奥氏体钢（316L），碳素钢（F-22，Fe-Si），铁素体/马氏体钢（HT-9和410）]，以及预期具有耐腐蚀性的几种实验性Fe-Si-Cr合金。根据材料和暴露位置的不同，材料会在LBE旋转电极或动态腐蚀池中在400、500、600和700摄氏度的温度下暴露100至1000小时。样品的重量变化和光学扫描电子显微镜或X射线分析被用来表征氧化膜厚度，腐蚀深度，微观结构和组成变化。腐蚀测试的结果证实了难熔金属（W，Ta和Mo）对LBE腐蚀的优异耐受性。用不锈钢（410、316L和HT-9）进行的测试将元素（例如Ni和Cr）传质到LBE中，导致材料降解。对于Fe-Si合金，由于铁的选择性溶解，在暴露于LBE的过程中，表面上形成了富硅层（如SiO2）。

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