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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Corrosion behavior of Alloy 690 and Alloy 693 in simulated nuclear high level waste medium
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Corrosion behavior of Alloy 690 and Alloy 693 in simulated nuclear high level waste medium

机译:690合金和693合金在模拟核高放废物介质中的腐蚀行为

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摘要

Nickel based alloys are candidate materials for the storage of high level waste (HLW) generated from reprocessing of spent nuclear fuel. In the present investigation Alloy 690 and Alloy 693 are assessed by potentiodynamic anodic polarization technique for their corrosion behavior in 3 M HNO_3, 3 M HNO_3 containing simulated HLW and in chloride medium. Both the alloys were found to possess good corrosion resistance in both the media at ambient condition. Microstructural examination was carried out by SEM for both the alloys after electrolytic etching. Compositional analysis of the passive film formed on the alloys in 3 M HNO_3 and 3 M HNO_3 with HLW was carried out by XPS. The surface of Alloy 690 and Alloy 693, both consists of a thin layer of oxide of Ni, Cr, and Fe under passivation in both the media. The results of investigation are presented in the paper.
机译:镍基合金是用于存储废核燃料后处理产生的高放废物(HLW)的候选材料。在本研究中,通过电位动力学阳极极化技术评估了690合金和693合金在3 M HNO_3,包含模拟HLW的3 M HNO_3和氯化物介质中的腐蚀行为。发现两种合金在环境条件下在两种介质中均具有良好的耐腐蚀性。电解蚀刻后,通过SEM对两种合金进行了显微组织检查。通过XPS对3M HNO_3和3M HNO_3合金中形成的钝化膜进行了成分分析。 690合金和693合金的表面均由在两种介质中均处于钝化状态的Ni,Cr和Fe氧化物薄层组成。本文介绍了调查结果。

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