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Re-oxidation behavior of Cr and V ions in the boiling nitric acid solution and acceleration effect on corrosion rate of stainless steel

机译:沸腾硝酸溶液中Cr和V离子的再氧化行为以及对不锈钢腐蚀速率的促进作用

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摘要

Nuclear fuel reprocessing is an important process for efficient usage of uranium resources. A large amount of nitric acid solution is used in Purex process which is adopted in Japanese nuclear fuel reprocessing plant (1). The materials of this plant are exposed in severe corrosive environment. Therefore, many types of equipment are made of corrosion resistant materials, i.e. austenitic stainless steel, titanium alloy and zirconium. Some reports pointed out that stainless steel was corroded at trans-passive state caused by several anodizing ions included in nitric acid solution (2-6). They introduced the characteristics of corrosion and improved materials in this environment. For example, Kajimura showed improved material reduced C, P and S content from austenitic stainless steel (6). And also, Cr, Ce, Ru Pu and Np were reported for the chemical species accelerated corrosion (3,5,7-9).rnAmong these chemicals, Pu and Np are radioactive and included in spent nuclear fuels. We have already reported that small amount of Np addition in the nitric acid solution accelerated corrosion rate dominantly (7). We suggested that Np was probably re-oxidized in the boiling nitric acid solution but the actual evidence was not obtained because of difficulties of handling Np. The solution containing Np must be handled in the specially designed laboratory so-called "hot Lab".rnBy the way, Cr and V were used substituting for these radioactive ion included in spent nuclear fuel (8-10). It was because that corrosion feature was similar as intergranular corrosion and the degree of accelerating corrosion rate was almost similar. It is expected that accurate analyses of the effect of these ions lead to understanding the mechanism of corrosion acceleration of Np ion addition.rnIn this report, we examined re-oxidation behavior in the boiling nitric acid solution and acceleration effect on corrosion rate of stainless steel using Cr and V ions
机译:核燃料后处理是有效利用铀资源的重要过程。在日本的核燃料后处理厂(1)中采用的Purex工艺中使用了大量的硝酸溶液。该工厂的材料暴露在严重的腐蚀环境中。因此,许多类型的设备是由耐腐蚀材料制成的,即奥氏体不锈钢,钛合金和锆。一些报告指出,由于硝酸溶液中包含的几种阳极氧化离子(2-6),不锈钢在超钝态下被腐蚀。他们介绍了这种环境下的腐蚀特征和改进的材料。例如,Kajimura表现出改进的材料可降低奥氏体不锈钢的C,P和S含量(6)。此外,据报道,Cr,Ce,Ru Pu和Np具有加速腐蚀的化学物种(3、5、7-9)。在这些化学物质中,Pu和Np具有放射性,并包含在乏核燃料中。我们已经报道过,在硝酸溶液中少量添加Np会显着加速腐蚀速率(7)。我们认为Np可能在沸腾的硝酸溶液中被重新氧化,但由于处理Np的困难而未能获得实际证据。含有Np的溶液必须在专门设计的实验室(所谓的“热实验室”)中进行处理。使用顺便说一下,用Cr和V代替了乏核燃料(8-10)中的这些放射性离子。这是因为该腐蚀特征与晶间腐蚀相似,并且加速腐蚀速率的程度几乎相似。期望准确地分析这些离子的作用可以了解Np离子加成腐蚀加速的机理。在本报告中,我们研究了沸腾硝酸溶液中的重氧化行为以及加速对不锈钢腐蚀速率的影响。使用Cr和V离子

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  • 来源
    《Oxide films》|2009年|p.23-30|共8页
  • 会议地点 Vienna(AT);Vienna(AT)
  • 作者单位

    Research Group for Corrosion Resistance Materials, Japan Atomic Energy Agency Tokai-Mura Ibaraki, 319-1195 JAPAN;

    Research Group for Corrosion Resistance Materials, Japan Atomic Energy Agency Tokai-Mura Ibaraki, 319-1195 JAPAN;

    Research Group for Corrosion Resistance Materials, Japan Atomic Energy Agency Tokai-Mura Ibaraki, 319-1195 JAPAN;

    Research Group for Corrosion Resistance Materials, Japan Atomic Energy Agency Tokai-Mura Ibaraki, 319-1195 JAPAN;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 TQ050.91;
  • 关键词

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