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几种合金材料在超临界水中的腐蚀行为研究
其他题名Corrosion Behavior of Several Alloys in Supercritical Water
孙明成
学位类型博士
导师韩恩厚
2009-12-15
学位授予单位中国科学院金属研究所
学位授予地点金属研究所
学位专业腐蚀科学与防护★
关键词不锈钢 镍基合金 铁素体/马氏体不锈钢 超临界水 氧化膜
摘要超临界水(SCW)是指当温度大于374.15oC、压力大于22.1MPa时水的状态。超临界水氧化(SCWO)是利用超临界水能与有机物、O2等完全互溶、传质快的特点,将有机废物迅速、彻底地氧化分解成无害的小分子物质的技术。SCW还具有比热容大、传热系数高的特点,可以作为超临界火电机组以及超临界水核反应堆的冷却介质,极大地提高热效率。在高温、高压环境下服役的超临界水设备的腐蚀问题成为阻碍超临界水工业化应用的关键问题之一。本文利用自主研制的超临界水腐蚀实验装置,开展了超临界水环境下的腐蚀实验。利用扫描电镜(SEM)、透射电镜(TEM)、X射线衍射(XRD)、X射线光电子谱(XPS)等技术手段,结合SCW性质的计算分析,系统表征了几种合金材料在SCW环境下的氧化腐蚀行为与腐蚀产物膜特征,深入研究了SCWO腐蚀过程和机理。 研究的材料为(1)316奥氏体不锈钢:作为结构材料,具有价格低、耐腐蚀性较好、工业应用广泛的特点,而且已经大量应用在高温高压水的环境中;(2)镍基合金625:在高温高压环境中具有优异的耐各种介质腐蚀的能力,是目前用于建造SCWO试验设备的主要材料之一,并且在SCW核电和SCW煤的汽化中具有潜在应用价值;(3)铁素体/马氏体不锈钢P92:具有优异的抗热疲劳性和优良的抗氧化性,目前大量应用于超临界和超超临界火电机组的主蒸汽管道上。 主要研究进展和结果如下: 1.设计建造了超高温超高压静态SCW釜,设计温度和压力达到700oC和35 MPa;改造升级了循环SCW腐蚀试验设备,实验温度和压力可以达到600oC和30 MPa。 2.利用循环SCW腐蚀试验设备研究了316不锈钢在含2% H2O2亚临界水(350oC)和超临界水(400oC、450oC、500oC)中的腐蚀增重规律,分析了腐蚀产物膜的形貌、结构和化学组成。发现316不锈钢在SCWO环境中的氧化膜较厚(0.6 μm-2.5 μm),为多层结构,从表层向内依次为(Fe,Cr)2O3/Fe3O4+FeCr2O4/Cr2O3/富Ni层/316 SS基体。基体和氧化膜界面处有一明显的富镍薄层。腐蚀产物膜截面的TEM分析表明,氧化膜外层为(Fe,Cr)2O3,靠近基体的一侧含有更多的Cr;氧化膜的内层为Fe3O4+FeCr2O4。富Fe外层是Fe向外传输的结果,富Cr内层是由氧向内传输形成的。由于Fe2O3和Cr2O3晶体结构相同,点阵常数也相近,因此Fe2O3中可以掺杂Cr成为(Fe,Cr)2O3;Fe3O4中掺杂Cr以后的晶体结构从反尖晶石结构的Fe3O4逐渐向尖晶石结构的FeCr2O4转变,而后者比前者更致密,抗氧化性能更好。 3.利用循环SCW腐蚀试验设备研究了镍基合金625在400oC-500oC超临界水中腐蚀增重规律及腐蚀产物膜特征。发现镍基合金625上形成的氧化膜相对于316不锈钢较薄(0.72 μm-1.42 μm),但是保护性能很好,腐蚀增重在氧化膜形成以后很缓慢。不同温度SCWO中形成的腐蚀产物膜的表面和截面的分析发现,产物膜为多层结构,外层是富Ni的氧化物,内层是富Cr的氧化物,确定氧化膜结构由表层向内为Ni(OH)2/NiO/NiCr2O4/Cr2O3/Alloy 625基体,其中富Ni外层可能是通过溶解/沉淀机制形成,富Cr的内层是由氧向内传输形成的。 4.利用超高温超高压静态SCW釜研究了P92在400oC-600oC之间,压力为25 MPa除氧SCW中的腐蚀增重行为,总暴露腐蚀时间为500 h。发现P92在除氧的SCW中的增重曲线符合抛物线规律。其腐蚀产物膜的厚度分别为3.8 μm(400oC)、11.2 μm(500oC)、18.3 μm(550oC)和45.3 μm(600oC)。腐蚀产物膜截面的TEM分析表明,P92在400oC SCW中暴露500 h后形成的氧化膜外层为Fe3O4,内层为Fe3O4+FeCr2O4。发现合金中的W元素氧化形成W3O8,以细小的晶粒嵌入在Fe3O4大晶粒中,可能对P92的抗氧化性能产生不利影响。600oC时形成的氧化膜过厚导致表面出现裂纹,成为氧通过氧化膜向内传输的一个快速通道,从而使P92在600oC时的增重比400oC-550oC时大得多。外层大颗粒的Fe3O4可能是通过Fe不断向外扩散形成的,氧向内传输形成了Fe3O4+FeCr2O4内层。 5.计算研究了SCW的性质,定性预测了SCW的压力对腐蚀速率的影响,研究了温度和压力对SCW中HCl的电离常数的影响。结果发现,增大压力会导致亚临界和SCW中合金腐蚀速率增大,特别是在临界点附近,压力变化显著影响腐蚀速率。HCl的电离常数随着SCW温度升高和压力的降低而减小,腐蚀速率也会减小。
其他摘要Supercritical water is the state of water when the temperature is above 374.15oC and the pressure is above 22.1MPa. Supercritical water oxidation (SCWO) can decompose and oxidize organic wastes into nontoxic products very quickly and thoroughly using supercritical water that becomes completely miscible with organics and O2. SCW coolant is a choice for fossil fuel power plants and nuclear reactors because of its large specific votume, good thermal conduction and high thermal efficiency. The SCW equipment serves in high temperatures and high pressures environment, so the severe reactor corrosion has become one of the key problems hindering the industrial application of SCWO. The corrosion experiments in SCW were conducted in self-developed SCW equipments. In this study, the corrosion behavior and the characterization of oxides grown on several alloys in SCW were investigated using scanning electron microscope (SEM), transmission electron microscopy (TEM), X-ray diffraction analyzer (XRD), X-ray photoelectron spectroscopy (XPS) combining with the calculation of SCW properties. The possible corrosion processes and mechanisms are also discussed. The chosen alloys for study are (1) 316 stainless steel: it is cheap and has been widely used in industry and also in high temperature and pressure water environments as structural material; (2) nickel-based alloy 625: it is commonly used for constructing the SCWO systems and it is candidate material for SCW nuclear reactor and SCW coal gasification due to its excellent anti-oxidation against high temperature and high pressure environments; (3) ferritic/martensitic steel P92: it is used in main steam tubes of SCW fossil fuel power plants due to its anti-fatigue and anti-oxidation. The main conclusions are as follows: 1. The SCW static equipments were designed and constructed which could operate at 700oC and 35MPa; the continuous SCWO equipment was upgraded which operated at 600oC and 30MPa. 2. The mass gain, morphologies and chemical compositions of oxides grown on 316 stainless steel exposed to 2% H2O2-containing sub-critical (350oC) and supercritical (400oC, 450oC, 500oC) water were investigated using the continuous SCWO equipment. The thickness of the oxides in SCW were between 0.6 μm and 2.5 μm and the structures were multi-layer consistent with the (Fe,Cr)2O3/Fe3O4+FeCr2O4/Cr2O3/Ni-enrichment/316 SS from the outer to inner layer. Ni enrichment was observed at the oxide/metal interface, especially at higher temperatures. TEM analyses showed that the outer oxide layer was (Fe,Cr)2O3 and the Cr content in (Fe,Cr)2O3 was enriched in the inner area of the oxide scales; the inner oxide layer was Fe3O4+FeCr2O4. The Fe-enriched outer layer was formed as a result of the Fe outward diffusion while the Cr-enriched inner layer was formed as a result of the O inward diffusion. α-Fe2O3 and Cr2O3 have the same space group and similar lattice constant, so α-Fe2O3 could contain some Cr and become (Fe,Cr)2O3 in the outer layer. The addition of Cr into Fe3O4 tends to transform the inverse spinel structure to the spinel structure. The FeCr2O4 spinel is much denser than the Fe3O4, which is believed to provide better oxidation resistance than the porous Fe3O4 layer. 3. The mass gain, morphologies and chemical compositions of oxides grown on nickel-based alloy 625 exposed to 400oC-500oC SCW were investigated using the continuous SCWO equipment. The oxides grown on nickel-based alloy 625 in 400oC-500oC SCW was thinner (0.72 μm-1.42 μm) and more protective compared with 316 stainless steel. The mass gain of alloy 625 was small once the oxides were formed. The analyses of the oxides grown on alloy 625 in SCW at different temperatures showed that the outer and inner oxide layer was Ni-enriched oxides and Cr-enriched oxides respectively. Multilayer structure was identified to consist of Ni(OH)2/NiO/NiCr2O4/Cr2O3/alloy 625 from outer to inner layer. The outer layer grew by dissolution and precipitation mechanism, while the Cr-enriched inner layer was formed by oxygen diffusing inward. 4. The corrosion behavior of P92 in 400oC-600oC and 25 MPa deaerated SCW after 500 h oxidation was studied using SCW static equipments. The mass gain diagram of P92 indicated a parabolic oxidation law. The thickness of the oxides grown on P92 were 3.8 μm (400oC), 11.2 μm (500oC), 18.3 μm (550oC) and 45.3 μm (600oC). TEM analyses showed that the outer layer was Fe3O4 and inner layer was Fe3O4+FeCr2O4 at 400oC SCW after 500 h oxidation. The element W in P92 became W3O8 and embedded in Fe3O4, which may produce detrimental effect to the oxidation resistance of P92. The oxide was thick (45.3 μm) at 600oC and resulted in cracks at the surface. The mass gain at 600oC was larger than those at 400oC-550oC because the cracks became effective channels for oxygen inward diffusion. The outer large Fe3O4 oxides may grow from the small Fe3O4 oxides at the outer/inner layer interface through Fe outward diffusion while the inner layer Fe3O4+FeCr2O4 was formed by oxygen inward diffusion. 5. The SCW properties and the effect of SCW pressures on the metal corrosion rate were studied through the calculated data. The effect of the SCW temperature and pressure on the dissociation of HCl was also studied. Increasing the pressure will increase the metal corrosion rate in sub-critical and supercritical water. At the area near the supercritical point, the effect of pressure on the corrosion rate was greater. The dissociation constant of HCl decreased when the SCW temperature increased or the SCW pressure decreased, which would decrease the corrosion.
页数127
语种中文
文献类型学位论文
条目标识符http://ir.imr.ac.cn/handle/321006/17277
专题中国科学院金属研究所
推荐引用方式
GB/T 7714
孙明成. 几种合金材料在超临界水中的腐蚀行为研究[D]. 金属研究所. 中国科学院金属研究所,2009.
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