690合金在线接触条件下的干态微幅冲击磨损研究
发布时间：2018-12-18 05:14
【摘要】：蒸汽发生器作为核电系统中一回路和二回路热传导的核心部件。其中高温高压介质的流动导致传热管与抗振条之间存在不可避免的微动磨损,使得传热管减薄降低使用。本论文通过模拟传热管与抗振条在不同温度下的微幅冲击磨损,研究其损伤行为特性。本文的研究结果对于丰富微动摩擦学的基础理论,对于提高核电站关键部件的使用具有指导意义。本文采用实验室自制的小型冲击试验机,以管／块试样线接触的方式对国产690合金管与405不锈钢试样进行了干态下的微幅冲击磨损试验。结合光学显微镜(OM)、三维形貌仪(ContourGT-I)、扫描电子显微镜(SEM)、能谱仪(EDX)、光电子能谱(XPS)等微观分析手段系统研究微幅冲击磨损机理,获得的主要结论如下：(1)在室温干态环境下,690合金管的冲击磨损机制主要是氧化磨损,粘着磨损和剥落；随着载荷增加,氧化、粘着磨损加剧,增加了材料的磨损,大大降低了材料的使用。主要体现随着载荷的增加,在O、Fe元素的增加,以及Ni、Cr元素的减少。冲击试验中造成材料接触区域损失量增大。(2)在室温干态环境下,690合金管在开始阶段的冲击磨损很小,随着冲击次数的增加,材料的微小变形的累积,以及反复冲压使得材料的磨损加剧,氧化效果增强。(3)在干态高温环境下,磨损在开始阶段较轻微,但是比同种工况的室温条件相比要严重。摩擦氧化在短时间就出现并迅速达到一个稳定状态,不会随着冲击次数的增加而变化。随着冲击次数的增加虽然磨损宽度、最大深度增加。由于磨屑得不到排除,形成的磨屑层保护了接触表面。
[Abstract]:Steam generator is the core component of heat conduction in primary circuit and secondary loop in nuclear power system. The flow of high temperature and high pressure medium leads to the inevitable fretting wear between the heat transfer tube and the anti-vibration bar, which reduces the use of the heat transfer tube. In this paper, the damage behavior of heat transfer tube and anti-vibration bar is studied by simulating the micro-impact wear of heat transfer tube and anti-vibration bar at different temperatures. The results of this paper are helpful to enrich the basic theory of fretting tribology and to improve the use of key components in nuclear power plants. In this paper, the micro-impact wear test of domestic 690 alloy tube and 405 stainless steel specimen in dry state was carried out by using a small scale impact testing machine made in the laboratory and by the way of tube / block sample line contact. The mechanism of micro-impact wear was studied by means of scanning electron microscope (SEM),) and scanning electron microscope (SEM), (OM), three-dimensional topography (ContourGT-I), (EDX), photoelectron spectroscopy (EDX), etc. The main conclusions are as follows: (1) the impact wear mechanism of 690 alloy tube is mainly oxidation wear, adhesion wear and spalling under dry condition at room temperature; With the increase of load, oxidation and adhesion wear are aggravated, and the wear of the material is increased, and the use of the material is greatly reduced. With the increase of load, the increase of Fe element and the decrease of Ni,Cr element. In the impact test, the material contact area loss is increased. (2) in the dry environment at room temperature, the impact wear of the 690 alloy tube at the beginning stage is very small, with the increase of the impact times, the accumulation of small deformation of the material. And repeated stamping makes the material wear worse and the oxidation effect enhanced. (3) in the dry state high temperature environment, the wear is slightly at the beginning, but more serious than the room temperature condition of the same working condition. Friction oxidation occurs in a short time and reaches a stable state rapidly, and does not change with the increase of impact times. The maximum depth increases with the increase of impact times, although the wear width increases. As the debris can not be excluded, the resulting debris layer protects the contact surface.
【学位授予单位】：西南交通大学
【学位级别】：硕士
【学位授予年份】：2015
【分类号】：TH117
本文编号：2385401
[Abstract]:Steam generator is the core component of heat conduction in primary circuit and secondary loop in nuclear power system. The flow of high temperature and high pressure medium leads to the inevitable fretting wear between the heat transfer tube and the anti-vibration bar, which reduces the use of the heat transfer tube. In this paper, the damage behavior of heat transfer tube and anti-vibration bar is studied by simulating the micro-impact wear of heat transfer tube and anti-vibration bar at different temperatures. The results of this paper are helpful to enrich the basic theory of fretting tribology and to improve the use of key components in nuclear power plants. In this paper, the micro-impact wear test of domestic 690 alloy tube and 405 stainless steel specimen in dry state was carried out by using a small scale impact testing machine made in the laboratory and by the way of tube / block sample line contact. The mechanism of micro-impact wear was studied by means of scanning electron microscope (SEM),) and scanning electron microscope (SEM), (OM), three-dimensional topography (ContourGT-I), (EDX), photoelectron spectroscopy (EDX), etc. The main conclusions are as follows: (1) the impact wear mechanism of 690 alloy tube is mainly oxidation wear, adhesion wear and spalling under dry condition at room temperature; With the increase of load, oxidation and adhesion wear are aggravated, and the wear of the material is increased, and the use of the material is greatly reduced. With the increase of load, the increase of Fe element and the decrease of Ni,Cr element. In the impact test, the material contact area loss is increased. (2) in the dry environment at room temperature, the impact wear of the 690 alloy tube at the beginning stage is very small, with the increase of the impact times, the accumulation of small deformation of the material. And repeated stamping makes the material wear worse and the oxidation effect enhanced. (3) in the dry state high temperature environment, the wear is slightly at the beginning, but more serious than the room temperature condition of the same working condition. Friction oxidation occurs in a short time and reaches a stable state rapidly, and does not change with the increase of impact times. The maximum depth increases with the increase of impact times, although the wear width increases. As the debris can not be excluded, the resulting debris layer protects the contact surface.
【学位授予单位】：西南交通大学
【学位级别】：硕士
【学位授予年份】：2015
【分类号】：TH117
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