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超临界水冷堆燃料包壳候选材料的耐腐蚀性能 被引量:3

Corrosion Behavior of Candidate SCWR Fuel Cladding Materials
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摘要 介绍了超临界水冷堆候选材料的相关腐蚀实验结果,并且讨论了每种候选材料在超临界水环境中的耐腐蚀性能。根据当前研究结果可知,高Cr含量的奥氏体不锈钢在超临界水中具有良好的抗腐蚀性能,因此其最有可能成为超临界水冷堆燃料包壳材料。 Corrosion performance of candidate clad materials for fuel of supercritical water-cooled reactor(SCWR) is reviewed with emphasis on that of four typical candidate alloys. According to the results presented in this paper, it is noted that the austenitic stainless steels with high Cr content show excellent corrosion resistance. Therefore, this kind of steels should be good candidate clad material for the fuel of SCWR.
出处 《中国腐蚀与防护学报》 CAS CSCD 北大核心 2014年第4期301-306,共6页 Journal of Chinese Society For Corrosion and Protection
基金 国家重点基础研究发展计划项目(2007CB209802)资助
关键词 超临界水冷堆 燃料包壳 腐蚀 氧化膜 supercritical water-cooled reactor,fuel cladding,corrosion,oxide film
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参考文献10

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