本文關(guān)鍵詞： 偏析 低偏析技術(shù) 微量元素 凝固區(qū)間　出處：《金屬學(xué)報》2017年05期 　論文類型：期刊論文

【摘要】：師昌緒先生領(lǐng)導(dǎo)的鑄造高溫合金團隊80年代初開始了低偏析技術(shù)的研究。將低偏析技術(shù)擴展應(yīng)用到火電大軸用30Cr2Ni4Mo V鋼、核電蒸發(fā)器傳熱管用690合金以及核燃料用鈾合金。通過解剖3支百噸常壓電弧爐熔煉的30Cr2Ni4Mo V鋼錠,發(fā)現(xiàn)控制微量元素O、Al含量可以顯著減少偏析。研究了690合金、U-6Nb合金與高碳鈾的凝固行為,S、N擴大了690合金的凝固溫度區(qū)間,并且S的影響大于N的影響;通過控制微量元素S、N含量可使690合金組織中成分均勻。在具有放射性元素的U-6Nb合金和高碳鈾中,計算了U-6Nb的凝固溫度區(qū)間為183℃;在高碳鈾中,當(dāng)C含量由0.01%增加到0.03%時,其凝固溫度區(qū)間由40℃增加到了75℃;C擴大了高碳鈾的凝固溫度區(qū)間。U-6Nb合金和高碳鈾的凝固偏析嚴(yán)重,采用低偏析技術(shù)控制U-6Nb合金中的C、N、O含量及高碳鈾中C、O含量,達到了減輕凝固偏析的效果,表明低偏析技術(shù)具有普適性。
[Abstract]:In 80s, the casting superalloy team led by Shi Changxu began the research of low segregation technology. The low segregation technology was extended to 30Cr2Ni4Mo steel for large shaft of thermal power plant. 690 alloy for heat transfer tube of nuclear power evaporator and uranium alloy for nuclear fuel. 30Cr2Ni4Mo V ingot melted by three hundred ton atmospheric arc furnace, It is found that the segregation can be significantly reduced by controlling the content of trace element O _ 2O _ 3.The solidification behavior of U-6Nb alloy of 690 alloy and high-carbon uranium alloy is studied. The solidification temperature range of alloy 690 is enlarged by Sn, and the influence of S is greater than that of N. The composition of alloy 690 can be homogenized by controlling the content of trace element Sno. The solidification temperature range of U-6Nb is calculated to be 183 鈩，

本文編號：1515232