Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1564875 | Journal of Nuclear Materials | 2015 | 11 Pages |
Abstract
The oxidation behavior of 316L stainless steel specimens after emery paper grounding, mechanical polishing, and electropolishing were investigated in simulated pressurized water reactor primary water at 310 °C for 120 and 500 h. Electropolishing afforded improved oxidation resistance especially during the early immersion stages. Duplex oxide films comprising a coarse Fe-rich outer layer and a fine Cr-rich inner layer formed on all specimens after 500 h of immersion. Only a compact layer was observed on the electropolished specimen after 120 h of immersion. The enrichment of chromium in the electropolished layer contributed to the passivity and protectiveness of the specimen.
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Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Guangdong Han, Zhanpeng Lu, Xiangkun Ru, Junjie Chen, Qian Xiao, Yongwu Tian,