Ni离子辐照国产ZIRLO合金的辐照性能研究
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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.
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.
引文
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[2]HALLSTADIUS L,JOHNSON S,LAHODA E.Progress in Nuclear Energy,2012,57(6):71.
[3]LIU Jianzhang.Nuclear Structure Materials[M].Beijing:Chemical Industry Press,2007:174.(in Chinese)(刘建章.核结构材料[M].北京:化学工业出版社,2007:174)
[4]ZHOU Jun,LI Zhongkui.Materials China,2014(Z1):554.(in Chinese)(周军,李中奎.中国材料进展,2014(Z1):554.)
[5]FLUSS M J,HOSEMANN P,MARIAN J.Characterization of Materials,2012.
[6]NORGETT M J,ROBINSON M T,TORRENS I M.Annual Book of ASTM Standards,1975.
[7]ZIEGLER J F.Nucl Instr&Meth,2004,219-220(1):1027.
[8]ONIMUS F,BECHADE J L.Comprehensive Nuclear Materials,2012:1.
[9]RYSSEL H.Ion Implantation Techniques[M].Heidelberg:Springer-Verlag Berlin Heidelberg,1982:177.
[10]OLIVER W C,PHARR G M.Journal of Materials Research,1992,7:1564.
[11]FISCHER-CRIPPS A C.Nanoindentation[M].New York:Springer-Verlag New York Inc,2004.