| 超临界二氧化碳环境中600合金和304不锈钢的均匀腐蚀行为研究 |
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| 引用本文： | 刘珠,龙家琛,郭相龙,苏豪展,王鹏,段振刚,马赵丹丹,张乐福.超临界二氧化碳环境中600合金和304不锈钢的均匀腐蚀行为研究[J].核动力工程,2023,44(1):89-96. |
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| 作者姓名： | 刘珠 龙家琛 郭相龙 苏豪展 王鹏 段振刚 马赵丹丹 张乐福 |
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| 作者单位： | 1.上海交通大学机械与动力工程学院，上海，200240 |
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| 摘 要： | 为遴选可用于超临界二氧化碳核反应堆的结构材料，通过实验研究了应用于传统核反应堆中的两种合金（600合金和304不锈钢）在650℃、20 MPa的超临界二氧化碳环境中的均匀腐蚀行为，运用增重法评价了材料的腐蚀动力学规律，采用扫描电镜、能谱仪和Ｘ射线衍射仪分析了氧化膜形貌、结构和化学成分。结果表明，两种材料的腐蚀增重均服从抛物线生长规律，其中600合金的耐腐蚀性能优于304不锈钢；腐蚀500 h后，600合金表面氧化物厚度约为5 μm，主要成分为NiCr2O4，结构致密，具有保护性，其氧化膜及基体中均未发现明显渗碳行为；腐蚀500 h后，304不锈钢表面氧化膜可达约45 μm，为双层结构，外层为Fe3O4，内层为NiFeCrO4，结构疏松，发生显著渗碳现象。本研究揭示了上述材料在超临界二氧化碳中的腐蚀机理，为超临界二氧化碳核反应堆结构材料的选择提供了数据支持。
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| 关 键 词： | 超临界二氧化碳 600合金 304不锈钢 均匀腐蚀 渗碳 |
| 收稿时间： | 2022-01-13 |
Study on Uniform Corrosion Behavior of 600 Alloy and 304 Stainless Steel in Supercritical Carbon Dioxide Environment |
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| Affiliation: | 1.School of Mechanical Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China2.Science and Technology on Rector System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China3.Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China |
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| Abstract: | In order to select the structural materials that can be used in the supercritical carbon dioxide nuclear reactor, the uniform corrosion behavior of two kinds of alloys (600 alloy and 304 stainless steel) used in the traditional nuclear reactor in the supercritical carbon dioxide environment at 650℃ and 20 MPa is studied through experiments. The corrosion kinetics of the material is evaluated by weight gain method, and the morphology, structure and chemical composition of the oxide film are analyzed by scanning electron microscope, energy dispersive spectrometer and X-ray diffractometer. The results show that the corrosion weight gain of the two materials obeys the parabolic growth law, and the corrosion resistance of 600 alloy is better than that of 304 stainless steel. After 500 h corrosion, the oxide thickness on the surface of 600 alloy is about 5 μm, the main component is NiCr2O4, which is compact in structure and protective. No obvious carburization is found in its oxide film and matrix; After 500 h corrosion, the oxidation film on 304 stainless steel surface can reach about 45 μm. It is a double-layer structure, the outer layer is Fe3O4, and the inner layer is NiFeCrO4. The structure is loose, and significant carburization occurs. This study reveals the corrosion mechanism of the above materials in supercritical carbon dioxide, and provides valuable data support for the selection of structural materials for supercritical carbon dioxide nuclear reactors. |
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