水化学对<strong>690</strong>镍基合金高温高压水腐蚀行为的影响

doi:10.11902/1005.4537.2024.414

中国腐蚀与防护学报

2025, Vol. 45

Issue (4): 1035-1040 CSTR: 32134.14.1005.4537.2024.414 DOI: 10.11902/1005.4537.2024.414

研究报告

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水化学对690镍基合金高温高压水腐蚀行为的影响

李顺平¹^,²^,³, 党莹²^,³, 洪晓峰²^,³, 宁方强⁴(

)

1 西南交通大学材料科学与工程学院成都 610031
2 中国核动力研究设计院核反应堆技术全国重点实验室成都 610213
3 中国核动力研究设计院先进核能技术全国重点实验室成都 610213
4 山东科技大学材料科学与工程学院山东省核电特种金属材料重点实验室青岛 266590

Effect of Water Chemistry on Corrosion Behavior of Nickel-based Alloy 690 in High Temperature High Pressure Water

LI Shunping¹^,²^,³, DANG Ying²^,³, HONG Xiaofeng²^,³, NING Fangqiang⁴(

)

1 College of Material Science and Technology, Southwest Jiaotong University, Chengdu 610031, China
2 National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, Chengdu 610213, China
3 State Key laboratory of Advanced Nuclear Energy Technology, Nuclear Power Institute of China, Chengdu 610213, China
4 Shandong Key Laboratory of Special Metallic Materials for Nuclear Equipment, School of Materials Science and Engineering, Shandong University of Science and Technology, Qingdao 266590, China

引用本文:

李顺平, 党莹, 洪晓峰, 宁方强. 水化学对690镍基合金高温高压水腐蚀行为的影响[J]. 中国腐蚀与防护学报, 2025, 45(4): 1035-1040.
Shunping LI, Ying DANG, Xiaofeng HONG, Fangqiang NING. Effect of Water Chemistry on Corrosion Behavior of Nickel-based Alloy 690 in High Temperature High Pressure Water[J]. Journal of Chinese Society for Corrosion and protection, 2025, 45(4): 1035-1040.

全文: PDF(7160 KB) HTML

摘要:

压水堆核电站蒸汽发生器传热管作为连接一回路和二回路的关键设备，其腐蚀行为受不同水化学参数的影响。本工作以传热管材料690镍基合金为研究对象，研究了溶解氧(DO)和溶解氢(DH)对690合金高温高压水腐蚀性能的影响。与在含1 μg/L DO的高温水中相比，690合金在含3 mg/L DO的高温水中，氧化膜中的富Cr氧化物不稳定，易溶于水，从而形成疏松多孔、不具有保护性的NiO层，导致氧化膜增厚；在含3 mg/L DH的高温水中，DH导致氧化膜中的Cr(OH)₃增多，Cr₂O₃减少，进而导致氧化膜保护性降低，氧化膜增厚。

关键词 ： 690合金, 腐蚀, 高温高压水, 溶解氧, 溶解氢

Abstract：

As the key equipment connecting the primary and secondary circuits of PWR nuclear power plants, the corrosion behavior of heat transfer tubes of steam generator (SG) would be affected by different water chemistry. Herein, the effect of dissolved oxygen (DO) and dissolved hydrogen (DH) on the corrosion performance of Nickel-based alloy 690 used as SG tubes in high temperature pressurized water were studied. In comparison with the formed oxide scale of the alloy formed in the high temperature water containing 1 μg/L DO, in the high temperature water containing 3 mg/L DO, the Cr-rich oxides in the formed oxide scale tend to be unstable and easily soluble in water, thus resulting in a thickened scale of loose, porous and non-protective NiO oxides. Furthermore, in the high temperature water containing 3 mg/L DH, DH leads to an increase of Cr(OH)₃ and a decrease of Cr₂O₃ in the formed oxide scales, as a result, the protectiveness of the oxide scales deteriorated, and the oxide scales grew thicker.

Key words： nickel-based alloy 690 corrosion high temperature high pressure water dissolved oxygen dissolved hydrogen

收稿日期: 2024-12-27 32134.14.1005.4537.2024.414

ZTFLH:

TL34

基金资助:国家自然科学基金(52105372);国家重点研发计划(2022YFB4301202-05)

通讯作者: 宁方强，E-mail：fqning16b@alum.imr.ac.cn，研究方向为核电结构材料腐蚀性能研究与评价

Corresponding author: NING Fangqiang, E-mail: fqning16b@alum.imr.ac.cn

作者简介: 李顺平，男，1988年生，博士生，助理研究员

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https://www.jcscp.org/CN/10.11902/1005.4537.2024.414 或 https://www.jcscp.org/CN/Y2025/V45/I4/1035

图1 690合金的微观组织

图2 690合金在290 ℃不同水化学参数的高温水中浸泡500 h后氧化膜的SEM形貌

图3 图2a2中位置A和B的能谱分析结果

图4 690合金在290 ℃不同水化学参数的高温水中浸泡500 h后氧化膜的XRD图谱

图5 690合金在290 ℃不同水化学参数的高温水中浸泡500 h后氧化膜的O深度分析

图6 690合金在290 ℃不同水化学参数的高温水中浸泡500 h后氧化膜的Ni、Cr和Fe深度分析

图7 690合金在1 μg/L DO和3 mg/L DH的高温水中浸泡500 h后氧化膜的O 1s和Cr 2p3/2 XPS谱及其分峰结果

图8 Fe-Cr-Ni合金在300 ℃水中的E-pH图[18]

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