运用扫描电子显微镜(SEM)、电子背散射衍射(EBSD)和取向成像显微技术(OIM)研究了690合金的晶界特征分布及晶界特征分布对晶间腐蚀性能的影响。低ΣCSL(coincidence site lattice,Σ≤29)晶界比例高(72.5%)时会出现大尺寸的晶粒团簇,团...运用扫描电子显微镜(SEM)、电子背散射衍射(EBSD)和取向成像显微技术(OIM)研究了690合金的晶界特征分布及晶界特征分布对晶间腐蚀性能的影响。低ΣCSL(coincidence site lattice,Σ≤29)晶界比例高(72.5%)时会出现大尺寸的晶粒团簇,团簇内部晶粒互有Σ3n取向差关系。当低ΣCSL晶界比例低(46.7%)时,这种晶粒团簇的大小和内含Σ3n晶界数量都降低。运用Palumbo-Aust标准统计晶界特征分布时,大尺寸的晶粒团簇之间的随机晶界的连通性几乎不会被打断;但运用Brandon标准统计时,这些随机晶界连通性明显被一些相对偏差较大的低ΣCSL晶界打断。低ΣCSL晶界比例高的样品比低ΣCSL晶界比例低的样品明显耐晶间腐蚀。展开更多
The oxidation behavior of alloy 690 exposed to high-temperature and high-pressure steam and water at 280℃ for 1 h was investigated by scanning electron microscopy （SEM）, atomic force microscopy （AFM） and X-ray ph...The oxidation behavior of alloy 690 exposed to high-temperature and high-pressure steam and water at 280℃ for 1 h was investigated by scanning electron microscopy （SEM）, atomic force microscopy （AFM） and X-ray photoelectron spectroscopy （XPS）. In high-temperature and high-pressure steam, the oxide film is composed of an outermost Ni-rich hydroxides layer, an intermediate layer of hydroxides and oxides enriched in Cr, an inner oxide layer. The film formed in high-temperature water is similar to that in steam, except for missing the Ni-rich hydroxides layer. Samples with different surface finishes （electropolished, mechanically polished, ground, and as-received） were prepared for comparison. A general increase of the oxide thickness with the degree of surface roughness is observed. The equivalent oxide thicknesses lie in the range of 100-200 nm for the as-received samples, 150-250 nm for the samples ground to 400# and 10-20 nm for the samples ground to 1500#, mechanically polished, and electropolished.展开更多
利用形变及热处理工艺提高了690合金的低Σ重位点阵(Coinc idence S ite Lattice,CSL)晶界比例,通过电子背散射衍射(EBSD)技术表征了由不同类型晶界构成的网络特征,结果表明通过晶界工程处理,能够形成以大尺寸"互有Σ3n取向关系晶...利用形变及热处理工艺提高了690合金的低Σ重位点阵(Coinc idence S ite Lattice,CSL)晶界比例,通过电子背散射衍射(EBSD)技术表征了由不同类型晶界构成的网络特征,结果表明通过晶界工程处理,能够形成以大尺寸"互有Σ3n取向关系晶粒的团簇"显微组织为特征的晶界网络分布,这种显微组织是再结晶过程中多重孪晶充分发展的结果。通过晶间腐蚀浸泡实验表明通过晶界工程处理的样品抗晶间腐蚀性能较未经过晶界工程处理的样品明显提高。腐蚀后样品的显微形貌表明大尺寸"互有Σ3n取向关系晶粒的团簇"能够阻止晶间腐蚀向样品内部扩展,并且能够保护下层的显微组织。展开更多
The impact fretting wear has largely occurred at nuclear power device induced by the flow-induced vibra- tion, and it will take potential hazards to the service of the equipment. However, the present study focuses on ...The impact fretting wear has largely occurred at nuclear power device induced by the flow-induced vibra- tion, and it will take potential hazards to the service of the equipment. However, the present study focuses on the tangential fretting wear of alloy 690 tubes. Research on impact fretting wear of alloy 690 tubes is limited and the related research is imminent. Therefore, impact fretting wear behavior of alloy 690 tubes against 304 stainless steels is investigated. Deionized water is used to simulate the flow environment of the equipment, and the dry envi- ronment is used for comparison. Varied analytical tech- niques are employed to characterize the wear and tribochemical behavior during impact fretting wear. Char- acterization results indicate that cracks occur at high impact load in both water and dry equipment; however, the water as a medium can significantly delay the cracking time. The crack propagation behavior shows a jagged shape in the water, but crack extended disorderly in dry equip- ment because the water changed the stress distribution and retarded the friction heat during the wear process. The SEM and XPS analysis shows that the main failure mechanisms of the tube under impact fretting are fatiguewear and friction oxidation. The effect of medium（water） on fretting wear is revealed, which plays a potential and promising role in the service of nuclear power device and other flow equipments.展开更多
文摘运用扫描电子显微镜(SEM)、电子背散射衍射(EBSD)和取向成像显微技术(OIM)研究了690合金的晶界特征分布及晶界特征分布对晶间腐蚀性能的影响。低ΣCSL(coincidence site lattice,Σ≤29)晶界比例高(72.5%)时会出现大尺寸的晶粒团簇,团簇内部晶粒互有Σ3n取向差关系。当低ΣCSL晶界比例低(46.7%)时,这种晶粒团簇的大小和内含Σ3n晶界数量都降低。运用Palumbo-Aust标准统计晶界特征分布时,大尺寸的晶粒团簇之间的随机晶界的连通性几乎不会被打断;但运用Brandon标准统计时,这些随机晶界连通性明显被一些相对偏差较大的低ΣCSL晶界打断。低ΣCSL晶界比例高的样品比低ΣCSL晶界比例低的样品明显耐晶间腐蚀。
基金supported by the Special Funds for the Major State Basic Research Projects(G2011CB610502)the National Natural Science Foundation of China (No.51025104)
文摘The oxidation behavior of alloy 690 exposed to high-temperature and high-pressure steam and water at 280℃ for 1 h was investigated by scanning electron microscopy （SEM）, atomic force microscopy （AFM） and X-ray photoelectron spectroscopy （XPS）. In high-temperature and high-pressure steam, the oxide film is composed of an outermost Ni-rich hydroxides layer, an intermediate layer of hydroxides and oxides enriched in Cr, an inner oxide layer. The film formed in high-temperature water is similar to that in steam, except for missing the Ni-rich hydroxides layer. Samples with different surface finishes （electropolished, mechanically polished, ground, and as-received） were prepared for comparison. A general increase of the oxide thickness with the degree of surface roughness is observed. The equivalent oxide thicknesses lie in the range of 100-200 nm for the as-received samples, 150-250 nm for the samples ground to 400# and 10-20 nm for the samples ground to 1500#, mechanically polished, and electropolished.
文摘利用形变及热处理工艺提高了690合金的低Σ重位点阵(Coinc idence S ite Lattice,CSL)晶界比例,通过电子背散射衍射(EBSD)技术表征了由不同类型晶界构成的网络特征,结果表明通过晶界工程处理,能够形成以大尺寸"互有Σ3n取向关系晶粒的团簇"显微组织为特征的晶界网络分布,这种显微组织是再结晶过程中多重孪晶充分发展的结果。通过晶间腐蚀浸泡实验表明通过晶界工程处理的样品抗晶间腐蚀性能较未经过晶界工程处理的样品明显提高。腐蚀后样品的显微形貌表明大尺寸"互有Σ3n取向关系晶粒的团簇"能够阻止晶间腐蚀向样品内部扩展,并且能够保护下层的显微组织。
基金Supported by National Natural Science Foundation of China(Grant Nos.51375407,U1530136,51627806)Shanghai Municipal Science and Technology Talent Program of China(Grant No.14R21421500)Young Scientific Innovation Team of Science and Technology of Sichuan(Grant No.2017TD0017)
文摘The impact fretting wear has largely occurred at nuclear power device induced by the flow-induced vibra- tion, and it will take potential hazards to the service of the equipment. However, the present study focuses on the tangential fretting wear of alloy 690 tubes. Research on impact fretting wear of alloy 690 tubes is limited and the related research is imminent. Therefore, impact fretting wear behavior of alloy 690 tubes against 304 stainless steels is investigated. Deionized water is used to simulate the flow environment of the equipment, and the dry envi- ronment is used for comparison. Varied analytical tech- niques are employed to characterize the wear and tribochemical behavior during impact fretting wear. Char- acterization results indicate that cracks occur at high impact load in both water and dry equipment; however, the water as a medium can significantly delay the cracking time. The crack propagation behavior shows a jagged shape in the water, but crack extended disorderly in dry equip- ment because the water changed the stress distribution and retarded the friction heat during the wear process. The SEM and XPS analysis shows that the main failure mechanisms of the tube under impact fretting are fatiguewear and friction oxidation. The effect of medium（water） on fretting wear is revealed, which plays a potential and promising role in the service of nuclear power device and other flow equipments.
