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Crevice Corrosion of Nickel Alloys for Steam Generator Tubing of Pressurized Water Reactors

机译:压水堆蒸汽发生器管镍合金的缝隙腐蚀

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Ni-Fe-Cr alloys, such as alloys N06600, N06690 and N08800, are used in steam generator tubing of nuclear power reactors due to their high mechanical strength and corrosion resistance at high temperature. Failure of those alloys is associated with crevices formed between tubing and tube sheet or tube support plates, or fouling formed during operation. In this work, the crevice corrosion susceptibility of these alloys was analyzed. Crevice corrosion was studied at atmospheric pressure in 5 M, 1 M, 0.1 M and 0.01 M NaCI solutions at 30 °C, 60 °C and 90 °C using artificially creviced specimens. Alloy specimens were polarized potentiodynamically up to 300 μA (`25 μA/cm~2) and held at that current for 2 hours; then the potential scan was reversed until reaching alloy repassivation. All the alloys suffered from crevice corrosion. Test reproducibility was higher under more aggressive conditions (i.e., higher temperature and chloride concentration). The repassivation potential decreased with increasing temperature and chloride concentration indicating higher crevice corrosion susceptibility. Crevice corrosion resistance increased in the order alloy N06690 < alloy N06600 < alloy N08800. Corrosion potential measurements and potentiodynamic polarization experiments were performed in simulated crevice-like solutions to understand these results.
机译:Ni-Fe-Cr合金,例如N06600,N06690和N08800合金,由于其较高的机械强度和高温下的耐腐蚀性而被用于核动力反应堆的蒸汽发生器管道中。这些合金的失效与管子和管板或管子支撑板之间形成的缝隙或操作过程中形成的结垢有关。在这项工作中,分析了这些合金的缝隙腐蚀敏感性。在30°C,60°C和90°C的人工腐蚀样品下,在大气压下于5 M,1 M,0.1 M和0.01 M NaCl溶液中研究了缝隙腐蚀。合金样品被电势极化至300μA(`25μA/ cm〜2),并在该电流下保持2个小时;然后反转电位扫描,直至达到合金钝化。所有的合金都遭受缝隙腐蚀。在更苛刻的条件下(即更高的温度和氯化物浓度),测试的再现性更高。随着温度和氯化物浓度的增加,再钝化电势降低,表明缝隙腐蚀敏感性更高。耐缝隙腐蚀性按合金N06690 <合金N06600 <合金N08800的顺序增加。在类似缝隙的溶液中进行腐蚀电位测量和电位动力学极化实验,以了解这些结果。

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