Ni离子辐照国产ZIRLO合金的辐照性能研究  

Study on Radiation Properties of Domestic ZIRLO Irradiated by Ni Heavy Ions

作　　者：白若玉 范平[1] 夏海鸿 袁大庆[1] 孔淑妍 张乔丽[1] 马海亮[1] 左翼[1] 温阿利 朱升云[1] 

机构地区：[1]中国原子能科学研究院,北京102413 [2]国家电投中央研究院,北京100029

出　　处：《原子核物理评论》2017年第3期630-635,共6页Nuclear Physics Review

基　　金：国家自然科学基金资助项目(11005158;91126002);国家国际科技合作专项项目(2015DFA50510);国家科技重大专项(2012ZX06004-005-005)~~

摘　　要：国产ZIRLO合金是CAP1400重要的燃料包壳管候选材料之一,因此需要在使用前对该材料进行辐照性能考验。研究了国产ZIRLO合金的辐照性能随辐照温度和损伤剂量的变化。辐照实验在中国原子能科学研究院HI-13串列加速器上,采用80 Me V的Ni离子进行,辐照产生的损伤采用透射电子显微镜、能量色散谱和纳米压痕法等方法表征。国产ZIRLO合金在300℃经10 dpa损伤剂量辐照后观察到均匀分布的析出颗粒,同样剂量在700℃辐照析出颗粒数目减少,析出相的主要成分为Nb。辐照后出现硬化现象,辐照损伤剂量越大,硬化程度越高;随着辐照温度升高,辐照硬化呈减小趋势。The domestic ZIRLO is a promising candidate of cladding materials for CAP1400. It is necessary to test its radiation properties before its use. In this paper, the radiation properties of the domestic ZIRLO have been studied as functions of irradiation temperature and dose respectively. The experiment was performed at the HI-13 tandem accelerator of China Institute of Atomic Energy by using 80 Me V Ni ions at different temperature and different dose. The transmission electron microscopy, electron dispersive spectroscopy and nano-indentation were used to characterize the radiation damage. The experimental results show that the precipitates are uniformly distributed at 10 dpa and 300 ℃, while at 700 ℃ the number of precipitates is reduced. Among all the precipitates,Nbisthe dominant element. Hardening phenomenon was also observed after irradiation, the higher the radiation dose, the higher the degree of hardening, and it illustrates a decreasing tendency with the increasing of the irradiation temperature.

关 键 词：锆合金包壳管 重离子辐照 微观结构分析 纳米压痕 

分 类 号：O482.1[理学—固体物理]