核電用316LN不銹鋼在不同溫度下的形變行為和機(jī)理
發(fā)布時(shí)間:2019-07-08 11:06
【摘要】:中國(guó)核電的發(fā)展路線以壓水堆為主,技術(shù)處在二:代,接近第三代。國(guó)際上所有核電站對(duì)安全性都有著嚴(yán)格的要求,且由于核電用材料服役環(huán)境復(fù)雜,其在選材上有著苛刻的條件。316LN不銹鋼具有優(yōu)良的耐腐蝕性及綜合力學(xué)性能,是第三代壓水堆一回路主管道和堆內(nèi)構(gòu)件的首選材料。本論文通過(guò)對(duì)相關(guān)文獻(xiàn)的調(diào)研,結(jié)合實(shí)際生產(chǎn)的需求,從以下幾個(gè)方面對(duì)核電用316LN不銹鋼進(jìn)行了研究。 首先,對(duì)核電用316LN不銹鋼的鍛材進(jìn)行了熱壓縮試驗(yàn),通過(guò)熱壓縮應(yīng)力-應(yīng)變曲線計(jì)算出熱激活能,建立了本構(gòu)方程,并繪制了熱加工圖,直觀地表明了熱加工參數(shù)優(yōu)先選擇能量耗散率較高的[區(qū)域。同時(shí),通過(guò)顯微組織分析,得到了高溫壓縮形變過(guò)程中的動(dòng)態(tài)再結(jié)晶規(guī)律。 其次,對(duì)316LN不銹鋼的鍛材和軋材從室溫到1000℃范圍內(nèi)進(jìn)行了拉伸試驗(yàn)。通過(guò)對(duì)應(yīng)力-應(yīng)變曲線和硬化速率-應(yīng)變曲線的分析,以及對(duì)斷口形貌和斷口附近的顯微硬度和組織的觀察分析,得到了不同溫度下拉伸形變的特點(diǎn)和機(jī)制。 在600℃以下溫度拉伸時(shí),鍛材和軋材的硬化速率-應(yīng)變曲線均可分為段:平穩(wěn)段、下降段和塑性失穩(wěn)段。鍛材初始組織中的高密度位錯(cuò)使得動(dòng)態(tài)回復(fù)速度加快,從而導(dǎo)致了鍛材的硬化-應(yīng)變曲線平穩(wěn)段中無(wú)明顯的上升部分。鍛材的屈服強(qiáng)度明顯高于軋材,這是由于鍛材初始組織中的高密度位錯(cuò)促進(jìn)了材料的動(dòng)態(tài)回復(fù),但還不足以消除初始組織對(duì)拉伸性能的影響。在此溫度段拉伸形變機(jī)制以滑移和孿晶為主,隨著溫度的升高,位錯(cuò)交滑移逐漸增多。 在700℃拉伸時(shí),其硬化速率-應(yīng)變曲線可以分為兩段:下降段和塑性失穩(wěn)段。600℃至700℃拉伸時(shí),氮、碳原子的擴(kuò)散速率與位錯(cuò)運(yùn)動(dòng)速率相近,對(duì)位錯(cuò)形成反復(fù)“釘軋”作用,使得鍛材和軋材均出現(xiàn)了動(dòng)態(tài)應(yīng)變時(shí)效現(xiàn)象,引起了硬化速率-應(yīng)變曲線鋸齒波狀的波動(dòng),鍛材在700℃時(shí)的波動(dòng)現(xiàn)象最為明顯。軋材700℃拉伸時(shí)由于位錯(cuò)交滑移導(dǎo)致試樣中出現(xiàn)了大量的位錯(cuò)塞積,而鍛材則出現(xiàn)位錯(cuò)網(wǎng)。位錯(cuò)運(yùn)動(dòng)機(jī)制的變化造成了,700℃時(shí)拉伸形變硬化行為的明顯不同和形變組織的較大差異。 800℃C以上伸時(shí),鍛材和軋材硬化速率-應(yīng)變曲線也可分為三段:快速下降段、平穩(wěn)段、塑性失穩(wěn)段。鍛材原始組織中的亞晶和高密度位錯(cuò)對(duì)1000℃時(shí)拉伸行為已沒(méi)有太大的影響。在此溫度段的軟化機(jī)制有高溫組織多邊形化和動(dòng)態(tài)再結(jié)晶兩種,鍛材中大量的亞晶和高密度位錯(cuò),使其具有更多的再結(jié)晶核心,從而導(dǎo)致其具有較短的快速下降階段。軋材在900℃,鍛材在950℃發(fā)生完全再結(jié)晶。 最后,對(duì)316LN不銹鋼的鍛材和軋材在350℃和600℃下不同應(yīng)力下500-2000小時(shí)進(jìn)行了預(yù)蠕變?cè)囼?yàn)。通過(guò)對(duì)預(yù)蠕變?cè)囼?yàn)后的試樣進(jìn)行性能測(cè)試及顯微分析,得到了性能和組織變化的規(guī)律。 在預(yù)蠕變過(guò)程中,溫度越高,時(shí)間越長(zhǎng),氮原子遷移偏聚越明顯。元素的擴(kuò)散偏聚對(duì)材料的組織和性能產(chǎn)生如下影響:造成基體層錯(cuò)能的提高,從而使擴(kuò)展位錯(cuò)變窄;氮和鉻的擴(kuò)散遷移在600℃保溫2000小時(shí)后形成了短程有序的鉻氮原子團(tuán),使得試樣中出現(xiàn)了位錯(cuò)對(duì);試樣顯微硬度上升;部分晶界出現(xiàn)了寬化,晶界處的硬度明顯要高于晶內(nèi);在氮原子的遷移以及長(zhǎng)時(shí)間受力下造成的位錯(cuò)變化的共同作用下,軋材的屈服強(qiáng)度有明顯的上升。 鍛材初始組織中的大量亞晶和高密度位錯(cuò)使預(yù)蠕變后的性能和組織產(chǎn)生了影響。高密度位錯(cuò)在預(yù)蠕變初期的回復(fù)作用使得鍛材在預(yù)蠕變500小時(shí)后顯微硬度上升幅度明顯低于軋材;亞晶界在預(yù)蠕變過(guò)程中發(fā)生了分解遷移,隨著時(shí)間延長(zhǎng),有的亞晶界因分解遷移變薄直至消失,這種分解使得亞晶界在高溫下易于滑動(dòng),但同時(shí)使得試樣中不同方向運(yùn)動(dòng)的位錯(cuò)增多,這些位錯(cuò)相遇時(shí)相互反應(yīng)能夠產(chǎn)生位錯(cuò)網(wǎng)。在350℃/20MPa預(yù)蠕變500小時(shí)的試樣出現(xiàn)了完整的近似四邊形位錯(cuò)網(wǎng),600℃/120MPa預(yù)蠕變500小時(shí)的試樣則出現(xiàn)了近似六邊形的波浪狀位錯(cuò)網(wǎng)。位錯(cuò)網(wǎng)是一個(gè)較為穩(wěn)定的結(jié)構(gòu),能夠延緩蠕變的發(fā)生。隨著預(yù)蠕變時(shí)間的延長(zhǎng),由于位錯(cuò)的持續(xù)運(yùn)動(dòng),這些位錯(cuò)網(wǎng)孔的直徑逐漸變小直至消失。
文內(nèi)圖片:
圖片說(shuō)明:(丨4鋼熱加工圖的各種應(yīng)用…I
[Abstract]:The development route of China's nuclear power is based on the PWR, and the technology is in the second generation, which is close to the third generation. All the nuclear power stations in the world have strict requirements for safety, and because of the complex service environment of nuclear power materials, it has harsh conditions in material selection. The 316LN stainless steel has excellent corrosion resistance and comprehensive mechanical properties. And is the preferred material of the third generation pressurized water reactor primary pipeline and the inner member of the reactor. Based on the investigation of the relevant literature and the demand of practical production, the 316LN stainless steel for nuclear power has been studied from the following aspects. In the first place, the thermal compression test is carried out on the forged material of the 316LN stainless steel for nuclear power, the thermal activation energy is calculated by the thermal compression stress-strain curve, the constitutive equation is established, and the hot working diagram is drawn, which shows that the preferential energy dissipation rate of the hot working parameter is higher[area And the dynamic recrystallization rule in the process of high-temperature compression deformation is obtained through the analysis of the micro-structure. Law. Second, the forged and rolled materials of 316LN stainless steel were pulled from room temperature to 1000 鈩,
本文編號(hào):2511545
文內(nèi)圖片:
圖片說(shuō)明:(丨4鋼熱加工圖的各種應(yīng)用…I
[Abstract]:The development route of China's nuclear power is based on the PWR, and the technology is in the second generation, which is close to the third generation. All the nuclear power stations in the world have strict requirements for safety, and because of the complex service environment of nuclear power materials, it has harsh conditions in material selection. The 316LN stainless steel has excellent corrosion resistance and comprehensive mechanical properties. And is the preferred material of the third generation pressurized water reactor primary pipeline and the inner member of the reactor. Based on the investigation of the relevant literature and the demand of practical production, the 316LN stainless steel for nuclear power has been studied from the following aspects. In the first place, the thermal compression test is carried out on the forged material of the 316LN stainless steel for nuclear power, the thermal activation energy is calculated by the thermal compression stress-strain curve, the constitutive equation is established, and the hot working diagram is drawn, which shows that the preferential energy dissipation rate of the hot working parameter is higher[area And the dynamic recrystallization rule in the process of high-temperature compression deformation is obtained through the analysis of the micro-structure. Law. Second, the forged and rolled materials of 316LN stainless steel were pulled from room temperature to 1000 鈩,
本文編號(hào):2511545
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