【摘要】：蒸汽發(fā)生器作為核電系統(tǒng)中一回路和二回路熱傳導(dǎo)的核心部件。其中高溫高壓介質(zhì)的流動導(dǎo)致傳熱管與抗振條之間存在不可避免的微動磨損,使得傳熱管減薄降低使用。本論文通過模擬傳熱管與抗振條在不同溫度下的微幅沖擊磨損,研究其損傷行為特性。本文的研究結(jié)果對于豐富微動摩擦學(xué)的基礎(chǔ)理論,對于提高核電站關(guān)鍵部件的使用具有指導(dǎo)意義。本文采用實(shí)驗(yàn)室自制的小型沖擊試驗(yàn)機(jī),以管／塊試樣線接觸的方式對國產(chǎn)690合金管與405不銹鋼試樣進(jìn)行了干態(tài)下的微幅沖擊磨損試驗(yàn)。結(jié)合光學(xué)顯微鏡(OM)、三維形貌儀(ContourGT-I)、掃描電子顯微鏡(SEM)、能譜儀(EDX)、光電子能譜(XPS)等微觀分析手段系統(tǒng)研究微幅沖擊磨損機(jī)理,獲得的主要結(jié)論如下：(1)在室溫干態(tài)環(huán)境下,690合金管的沖擊磨損機(jī)制主要是氧化磨損,粘著磨損和剝落；隨著載荷增加,氧化、粘著磨損加劇,增加了材料的磨損,大大降低了材料的使用。主要體現(xiàn)隨著載荷的增加,在O、Fe元素的增加,以及Ni、Cr元素的減少。沖擊試驗(yàn)中造成材料接觸區(qū)域損失量增大。(2)在室溫干態(tài)環(huán)境下,690合金管在開始階段的沖擊磨損很小,隨著沖擊次數(shù)的增加,材料的微小變形的累積,以及反復(fù)沖壓使得材料的磨損加劇,氧化效果增強(qiáng)。(3)在干態(tài)高溫環(huán)境下,磨損在開始階段較輕微,但是比同種工況的室溫條件相比要嚴(yán)重。摩擦氧化在短時(shí)間就出現(xiàn)并迅速達(dá)到一個(gè)穩(wěn)定狀態(tài),不會隨著沖擊次數(shù)的增加而變化。隨著沖擊次數(shù)的增加雖然磨損寬度、最大深度增加。由于磨屑得不到排除,形成的磨屑層保護(hù)了接觸表面。
[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.
【學(xué)位授予單位】：西南交通大學(xué)
【學(xué)位級別】：碩士
【學(xué)位授予年份】：2015
【分類號】：TH117

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本文編號：2385401