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Ni离子辐照国产ZIRLO合金的辐照性能研究

白若玉 范平 夏海鸿 袁大庆 孔淑妍 张乔丽 马海亮 左翼 温阿利 朱升云

白若玉, 范平, 夏海鸿, 袁大庆, 孔淑妍, 张乔丽, 马海亮, 左翼, 温阿利, 朱升云. Ni离子辐照国产ZIRLO合金的辐照性能研究[J]. 原子核物理评论, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
引用本文: 白若玉, 范平, 夏海鸿, 袁大庆, 孔淑妍, 张乔丽, 马海亮, 左翼, 温阿利, 朱升云. Ni离子辐照国产ZIRLO合金的辐照性能研究[J]. 原子核物理评论, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
BAI Ruoyu, FAN Ping, XIA Haihong, YUAN Daqing, KONG Shuyan, Zhang Qiaoli, MA Hailiang, ZUO Yi, WEN Ali, ZHU Shengyu. Study on Radiation Properties of Domestic ZIRLO Irradiated by Ni Heavy Ions[J]. Nuclear Physics Review, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
Citation: BAI Ruoyu, FAN Ping, XIA Haihong, YUAN Daqing, KONG Shuyan, Zhang Qiaoli, MA Hailiang, ZUO Yi, WEN Ali, ZHU Shengyu. Study on Radiation Properties of Domestic ZIRLO Irradiated by Ni Heavy Ions[J]. Nuclear Physics Review, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630

Ni离子辐照国产ZIRLO合金的辐照性能研究

doi: 10.11804/NuclPhysRev.34.03.630
基金项目: 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)
详细信息
    作者简介:

    白若玉(1990-),女,山西太原人,博士研究生,从事粒子物理与原子核物理研究;E-mail:ruoyub@163.com

  • 中图分类号: O482.1

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

Funds: National Natural Science Foundation of China (11005158, 91126002); International S&T Cooperation Program of China (2015DFA50510); National Science and Technology Major Project (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 MeV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 MeV 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.
  • [1] ZHAO Wenjin, ZHOU Bangxin, MIAO Zhi,et al. Atomic Energy Science and Technology. 2005, 39(S1):2. (in Chinese). (赵文金, 周邦新, 苗志, 等. 原子能科学技术, 2005, 39(S1):2)
    [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, BÉCHADE J L. Comprehensive Nuclear Mate-rials, 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.
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出版历程
  • 收稿日期:  2016-12-06
  • 修回日期:  2017-04-06
  • 刊出日期:  2017-07-18

Ni离子辐照国产ZIRLO合金的辐照性能研究

doi: 10.11804/NuclPhysRev.34.03.630
    基金项目:  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)
    作者简介:

    白若玉(1990-),女,山西太原人,博士研究生,从事粒子物理与原子核物理研究;E-mail:ruoyub@163.com

  • 中图分类号: O482.1

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 MeV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 MeV 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.

English Abstract

白若玉, 范平, 夏海鸿, 袁大庆, 孔淑妍, 张乔丽, 马海亮, 左翼, 温阿利, 朱升云. Ni离子辐照国产ZIRLO合金的辐照性能研究[J]. 原子核物理评论, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
引用本文: 白若玉, 范平, 夏海鸿, 袁大庆, 孔淑妍, 张乔丽, 马海亮, 左翼, 温阿利, 朱升云. Ni离子辐照国产ZIRLO合金的辐照性能研究[J]. 原子核物理评论, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
BAI Ruoyu, FAN Ping, XIA Haihong, YUAN Daqing, KONG Shuyan, Zhang Qiaoli, MA Hailiang, ZUO Yi, WEN Ali, ZHU Shengyu. Study on Radiation Properties of Domestic ZIRLO Irradiated by Ni Heavy Ions[J]. Nuclear Physics Review, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
Citation: BAI Ruoyu, FAN Ping, XIA Haihong, YUAN Daqing, KONG Shuyan, Zhang Qiaoli, MA Hailiang, ZUO Yi, WEN Ali, ZHU Shengyu. Study on Radiation Properties of Domestic ZIRLO Irradiated by Ni Heavy Ions[J]. Nuclear Physics Review, 2017, 34(3): 630-635. doi: 10.11804/NuclPhysRev.34.03.630
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