王瑞,霍同龙,田真真,刘鑫,孙昌帅,钱保治.Inconel690合金在高温苛性碱溶液中的腐蚀行为[J].表面技术,2025,54(10):105-115, 150.
WANG Rui,HUO Tonglong,TIAN Zhenzhen,LIU Xin,SUN Changshuai,QIAN Baozhi.Corrosion Behavior of Inconel690 Alloy in High Temperature Caustic Alkaline Solution[J].Surface Technology,2025,54(10):105-115, 150 |
| Inconel690合金在高温苛性碱溶液中的腐蚀行为 |
| Corrosion Behavior of Inconel690 Alloy in High Temperature Caustic Alkaline Solution |
| 投稿时间：2024-07-14 修订日期：2024-12-26 |
| DOI：10.16490/j.cnki.issn.1001-3660.2025.10.008 |
| 中文关键词: 蒸汽发生器 609合金 高温 碱性溶液 均匀腐蚀 腐蚀速率 |
| 英文关键词:steam generator 690 alloy high temperature alkaline solution uniform corrosion corrosion rate |
| 基金项目:中国博士后基金面上项目(2024M750723) |
| 作者 | 单位 |
| 王瑞 | 山东科技大学 机械电子工程学院，山东 青岛 266590;河钢集团有限公司，石家庄 050023 |
| 霍同龙 | 山东科技大学 机械电子工程学院，山东 青岛 266590 |
| 田真真 | 青岛天河制造业转型升级研究院有限公司，山东 青岛 266400 |
| 刘鑫 | 山东科技大学 机械电子工程学院，山东 青岛 266590 |
| 孙昌帅 | 山东科技大学 机械电子工程学院，山东 青岛 266590 |
| 钱保治 | 山东科技大学 机械电子工程学院，山东 青岛 266590;上海核电试验中心，上海 201413 |
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| Author | Institution |
| WANG Rui | College of Mechanical and Electronic Engineering, Shandong University of Science and Technology, Shandong Qingdao 266590, China;HBIS Group Co., Ltd., Shijiazhuang 050023, China |
| HUO Tonglong | College of Mechanical and Electronic Engineering, Shandong University of Science and Technology, Shandong Qingdao 266590, China |
| TIAN Zhenzhen | Qingdao Tianhe Manufacturing Transformation and Upgrading Research Institute Co., Ltd., Shandong Qingdao 266400, China |
| LIU Xin | College of Mechanical and Electronic Engineering, Shandong University of Science and Technology, Shandong Qingdao 266590, China |
| SUN Changshuai | College of Mechanical and Electronic Engineering, Shandong University of Science and Technology, Shandong Qingdao 266590, China |
| QIAN Baozhi | College of Mechanical and Electronic Engineering, Shandong University of Science and Technology, Shandong Qingdao 266590, China;Shanghai Nuclear Equipment Test Center, Shanghai 201413, China |
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| 中文摘要: |
| 目的 研究Inconel 690合金在高温苛性碱溶液中的腐蚀行为。方法 采用水循环系统的高压釜设备模拟压水堆(PWR)真实工况，设计了二回路水环境(285 ℃)、320 ℃偏离工况水环境、次临界水环境(360 ℃)以及不同pH值(pH=7、pH=9.8、pH=10.6)实验方案;通过SEM、EDS和XRD分析了氧化膜形貌及成分、元素含量和腐蚀机理。结果 在二回路水环境下，690合金在pH=9.8和pH=10.6水环境下的表面氧化物形状相似，表现为分布均匀的絮状氧化物，并且在絮状氧化物中离散分布着薄片状的氧化物颗粒，而在纯水(pH=7)环境下的氧化物则呈现单纯絮状;在320 ℃偏离工况水环境下，690合金形成的外层氧化物均为片状，并有不规则颗粒状氧化物生成;在次临界水环境(360 ℃)下，随着温度的升高，690合金表面的氧化物尺寸也在逐渐增大，但形貌并没有太大变化。结论 690合金在高温水环境中形成了双层氧化膜，初期内外层氧化膜分别为Cr2O3和Fe(OH)2、Ni(OH)2，由于固态氧化和金属溶解及沉积机制，最终形成Cr2O3、Cr(OH)2为主和微量(Nix,Fe1−x)Cr2O4的内层氧化膜以及Fe(OH)2、Ni(OH)2、NiFe2O4为主和少量NiO、FeO、Fe2O3的外层氧化膜;pH=7和pH=10.6时，320 ℃偏离工况水环境下均匀腐蚀速率最低;pH=9.8时，次临界水环境(360 ℃)下均匀腐蚀速率最低。 |
| 英文摘要: |
| The steam generator heat transfer tube is a heat exchange hub between the primary circuit and the secondary circuit of the pressurized water reactor (PWR). There is high temperature and high pressure alkaline solution in the service environment. In view of this, the corrosion behavior of Inconel 690 alloy in high temperature caustic alkaline solution was studied in this paper. The autoclave equipment with a water circulation system was used to simulate the real working conditions of PWR. The experimental schemes of secondary loop water environment (285 ℃), 320 ℃ off-condition water environment, sub-critical water environment (360 ℃) and different pH values (pH=7, pH=9.8, pH=10.6) were designed, and the uniform corrosion properties of the corresponding 690 alloy were tested. The morphology, composition, element content and corrosion mechanism of the oxide film were analyzed by SEM, EDS and XRD, and the corrosion rate under three working conditions was calculated. The uniform corrosion rate of alloy 690 at three temperatures were obtained. In the secondary loop water environment, the surface oxides of alloy 690 in pH=9.8 and pH=10.6 water environments were similar in shape, showing a uniform distribution of flocculent oxides, and discretely distributed in flocculent oxides. The flake-like oxide particles were about 0.3 μm in size, while the oxides in the pure water (pH=7) environment were pure flocculent. Combined with EDS results, the Cr content of flocculent oxides was higher. Under the 320 ℃ off-condition water environment, the outer oxides formed by 690 alloy were all flakes, and irregular granular oxides were formed. Compared with the outer oxide film, the Cr content of the inner oxide film was slightly higher, while the Fe content was slightly lower. In the sub-critical water environment (360 ℃), with the increase of temperature, the oxide size on the surface of 690 alloy was also gradually increasing. Compared with the 320 ℃ off-condition environment, the number of granular oxides under the sub-critical water environment was also more, but the morphology did not change much. In the secondary loop water environment, the uniform corrosion rates of pure water (pH=7), pH = 9.8 and pH =10.6 were 0.015, 0.013 and 0.004 mg/(dm2.h1/2), respectively. At 320 ℃, the uniform corrosion rates were 0.004, 0.008, 0.002 mg/(dm2.h1/2), respectively. In the sub-critical water environment, the uniform corrosion rates were 0.010, 0.002 and 0.011 mg/(dm2.h1/2), respectively. In conclusion, in the simulated secondary loop water environment, the surface of 690 alloy is uniformly distributed flocculent oxides, and flake oxides are dispersed in the flocculent oxides. With the increase of temperature, under the 320 ℃ off-condition environment, the flocculent oxide disappears, but the flake/leafy oxide increases and the size also increases. In the sub-critical water environment (360 ℃), the surface oxides are granular and not dense. A double-layer oxide film is formed on the surface of alloy 690 in the high temperature water environment. At the initial stage, the inner and outer oxide films are Cr2O3, Fe(OH)2 and Ni(OH)2, respectively. Due to the mechanism of solid-state oxidation and metal dissolution and deposition, the inner oxide film with Cr2O3 and Cr(OH)2 as the main and trace (Nix, Fe1−x)Cr2O4 as the main and the outer oxide film with Fe(OH)2, Ni(OH)2 and NiFe2O4 as the main and a small amount of NiO, FeO and Fe2O3 as the main are formed. When pH=7 and pH=10.6, the uniform corrosion rate is the lowest at 320 ℃. When pH=9.8, the uniform corrosion rate under the sub-critical water environment (360 ℃) is the lowest. |
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