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核反应堆压力容器模拟钢中富Cu纳米团簇析出早期阶段的研究
引用本文:王伟,朱娟娟,林民东,周邦新,刘文庆. 核反应堆压力容器模拟钢中富Cu纳米团簇析出早期阶段的研究[J]. 北京科技大学学报, 2010, 32(1)
作者姓名:王伟  朱娟娟  林民东  周邦新  刘文庆
作者单位:1. 上海大学材料研究所,上海,200072;上海工程技术大学材料工程学院,上海,201620
2. 上海大学材料研究所,上海,200072
基金项目:国家重点基础研究发展计划资助项目(No.2006CB605003);;国家自然科学基金重点资助项目(No.50931003);;上海市重点学科建设资助项目(No.S30107)
摘    要:采用调质处理后热时效模拟方法,用原子探针层析成像技术研究了核反应堆压力容器模拟钢中富铜纳米团簇的析出过程.模拟钢经880℃加热水淬,660℃高温回火调质处理,并经400℃时效处理1000 h后基体中析出了富铜纳米团簇.使用MSEM(maximum separation envelope method)方法重点研究了富铜纳米团簇在析出早期阶段成分变化规律.结果表明,富铜纳米团簇容易在镍含量较高的位置形核,并随着富铜纳米团簇中铜原子聚集程度的增加,纳米团簇中心处铜含量逐渐增加,镍含量逐渐减少;在纳米团簇与α--Fe基体界面处,镍和锰含量逐渐增加,形成了富镍和富锰包裹富铜纳米团簇的结构.结合实验结果讨论了压力容器钢中合金元素镍及杂质元素磷会增加中子辐照脆化敏感性的原因.

关 键 词:压力容器模拟钢  原子探针层析成像  时效处理  富Cu纳米团簇  

Study on the early-stage of copper-rich nano-clusters precipitation in model nuclear reactor pressure vessel steel
WANG Wei,ZHU Juan-juan,LIN Min-dong,ZHOU Bang-xin,LIU Wen-qing. Study on the early-stage of copper-rich nano-clusters precipitation in model nuclear reactor pressure vessel steel[J]. Journal of University of Science and Technology Beijing, 2010, 32(1)
Authors:WANG Wei  ZHU Juan-juan  LIN Min-dong  ZHOU Bang-xin  LIU Wen-qing
Abstract:Early-stage formation of Cu-rich nano-clusters in thermal aging nuclear reactor model pressure vessel steel quenched and tempered was investigated by atom probe tomography (APT). After the initial heat treatment at 880 ℃ for 0.5 h and water quenching, the materials were tempered for 10 h at 660 ℃ and air cooled. Cu-rich nano-clusters were observed in the samples aged at 400 ℃ for 1 000 h. The change in composition of the steel in the early-stage of precipitation of Cu-rich nano-clusters was studied by the maximum separation envelope method (MSEM). Cu nanoclusters are observed to form from high nickel regions. The Cu concentration increases and the Ni concentration decreases at the central cores with increasing Cu atoms congregation. Ni and Mn atoms aggregation on the exterior side of the cluster/matrix interface is also evident. Based on experimental results, the reason that Ni and P can increase the sensitivity to neutron irradiation embrittlement of the nuclear reactor pressure vessel steel is discussed.
Keywords:nuclear reactor pressure vessel steel  atom probe tomography (APT)  thermal aging  Cu-rich nano-clusters
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