模拟压水堆二回路水环境中温度对690合金电化学腐蚀行为的影响

doi:10.11902/1005.4537.2015.032

中国腐蚀与防护学报

2016, Vol. 36

Issue (2): 113-120 DOI: 10.11902/1005.4537.2015.032

本期目录 | 过刊浏览

模拟压水堆二回路水环境中温度对690合金电化学腐蚀行为的影响

汪家梅¹,陆辉¹,段振刚¹,张乐福¹(

),孟凡江²,徐雪莲²

1. 上海交通大学核能科学与工程学院上海 200240
2. 上海核工程研究设计院上海 200233

Effect of Temperature on Electrochemical Behavior of Alloy 690 in Simulated PWR Secondary Circuit Water

Jiamei WANG¹,Hui LU¹,Zhengang DUAN¹,Lefu ZHANG¹(

),Fanjiang MENG²,Xuelian XU²

1. School of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai 200240, China
2. Shanghai Nuclear Engineering Research &Design Institute, Shanghai 200233, China

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摘要:

通过EIS和动电位极化曲线的测量,并结合SEM观察、EDS和XPS分析,研究了模拟压水堆核电站 (PWR) 二回路服役水环境异常工况 (100 μg/L DO+100 μg/L Cl^-+ETA) 中溶液温度 (150~285 ℃) 对690合金电化学腐蚀行为的影响机理。结果表明：温度升高,690合金自腐蚀电位降低,腐蚀电流密度增加,钝化电位区间缩短;表面氧化膜厚度增加,颗粒增大,双层氧化膜特征越明显,但致密度和稳定性降低,导致其耐蚀性降低,合金腐蚀速率增加。

关键词 ： 690合金, 压水堆, 高温电化学腐蚀, 二回路

Abstract：

The effect of temperature (150~285 ℃) on the electrochemical corrosion behavior of Alloy 690 in stimulated pressurized water reactor (PWR) secondary circuit water environments was investigated by means of EIS, potentiodynamic polarization curves, SEM with EDS and XPS. The results revealed that, with the increasing temperature, the free corrosion potential decreased, corrosion current density increased, passive potential region shrank, the thicknesses of oxide scales and the size of oxide particles increased. Meanwhile, the double-layer characteristics of oxide scales became more obvious, but the compactness and stability of oxide scales degraded dramatically, resulting in the deterioration of corrosion resistance and the increase of corrosion rate of Alloy 690.

Key words： Alloy 690 PWR high-temperature electrochemical corrosion secondary circuit water

基金资助:大型先进压水堆核电站重大专项项目 (2010ZX06004-01) 资助

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引用本文:

汪家梅,陆辉,段振刚,张乐福,孟凡江,徐雪莲. 模拟压水堆二回路水环境中温度对690合金电化学腐蚀行为的影响[J]. 中国腐蚀与防护学报, 2016, 36(2): 113-120.
Jiamei WANG, Hui LU, Zhengang DUAN, Lefu ZHANG, Fanjiang MENG, Xuelian XU. Effect of Temperature on Electrochemical Behavior of Alloy 690 in Simulated PWR Secondary Circuit Water. Journal of Chinese Society for Corrosion and protection, 2016, 36(2): 113-120.

链接本文:

https://www.jcscp.org/CN/10.11902/1005.4537.2015.032 或 https://www.jcscp.org/CN/Y2016/V36/I2/113

图1 试样示意图

图2 实验回路示意图

图3 690合金在模拟PWR二回路高温高压水 (100 μg/L DO+100 μg/L Cl-+ETA) 中不同温度下的EIS谱

图4 拟合690合金EIS结果的等效电路图

图5 690合金的溶液电阻和极化电阻随温度的变化

图6 690合金在模拟PWR二回路水中不同温度下的极化曲线

图7 690合金的电化学参数随温度的变化

图8 钝化电流密度Ip与温度的Arrhenius关系

图9 690合金在模拟PWR二回路水中不同温度下浸泡30 h后的氧化膜形貌

表1 690合金在模拟PWR二回路水中不同温度下氧化膜的EDS结果

图10 690合金氧化膜中主要组成元素的原子分数随溅射深度的变化

图11 690合金氧化膜中主要元素的XPS谱

图12 690合金双层氧化膜结构示意图

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