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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Understanding long-term corrosion of Alloy 22 container in the potential Yucca Mountain repository for high-level nuclear waste disposal
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Understanding long-term corrosion of Alloy 22 container in the potential Yucca Mountain repository for high-level nuclear waste disposal

机译:了解潜在的丝兰山仓库中用于高级别核废料处置的22号合金容器的长期腐蚀

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Alloy 22 (Ni-22Cr-13Mo-3W-4Fe) is the candidate material for the waste package outer container in a potential geologic repository for high-level nuclear waste disposal at Yucca Mountain, Nevada. This alloy exhibits very low corrosion rates in the absence of environmental conditions promoting crevice corrosion. However, there are uncertainties regarding Alloy 22's corrosion performance when general corrosion rates and susceptibility to crevice corrosion are extrapolated to a geological time period (e.g. 10(5) years). This paper presents an analysis of available literature information relevant to the long-term extrapolation of general corrosion processes and the crevice corrosion behavior of Alloy 22, under potential repository environments. For assessment of general corrosion rates, potential degradation processes causing the loss of the long-term persistence of passive film formed are considered. For crevice corrosion, induction time, and the extent of susceptibility and opening area, are considered. Disclaimer: The US Nuclear Regulatory Commission (NRC) staff views expressed herein are preliminary and do not constitute a final judgment or determination of the matters addressed nor of the acceptability of a license application for a geologic repository at Yucca Mountain. The paper describes work performed by the Center for Nuclear Waste Regulatory Analyses (CNWRA) for NRC under Contract Number NRC-02-02-012. The activities reported here were performed by CNWRA on behalf of the NRC office of Nuclear Material Safety and Safeguards, Division of High Level Waste Repository Safety. This paper is an independent product of the CNWRA and does not necessarily reflect the view or regulatory position of the NRC.
机译:22号合金(Ni-22Cr-13Mo-3W-4Fe)是内华达州尤卡山的潜在核处置库中用于高级核废料处置的潜在废物处置包外部容器的候选材料。在缺乏促进缝隙腐蚀的环境条件下,该合金的腐蚀速率非常低。但是,当将一般腐蚀速率和对缝隙腐蚀的敏感性推算到地质时期(例如10(5)年)时,合金22的腐蚀性能存在不确定性。本文对在潜在的储存环境下与一般腐蚀过程的长期外推以及22号合金的缝隙腐蚀行为有关的可用文献信息进行了分析。为了评估一般腐蚀速率,考虑了可能导致形成的钝化膜长期持久性丧失的潜在降解过程。对于缝隙腐蚀,要考虑诱导时间以及磁化率和开口面积的范围。免责声明:本文中表达的美国核监管委员会(NRC)工作人员观点是初步的,并不构成对所解决事项的最终判断或确定,也不构成对丝兰山地质仓库的许可申请的可接受性。该文件描述了NRC的核废料监管分析中心(CNWRA)根据合同号NRC-02-02-012进行的工作。 CNWRA代表NRC核材料安全和保障局高级废物处置库安全司执行了此处报告的活动。本文是CNWRA的独立产品,不一定反映NRC的观点或监管立场。

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