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γ辐照后硼硅酸盐玻璃的吸收光谱研究

孙梦利 刘枫飞 杜鑫 袁伟 律鹏 赵彦 张冰焘 张晓阳 陈亮 王铁山 彭海波

孙梦利, 刘枫飞, 杜鑫, 袁伟, 律鹏, 赵彦, 张冰焘, 张晓阳, 陈亮, 王铁山, 彭海波. γ辐照后硼硅酸盐玻璃的吸收光谱研究[J]. 原子核物理评论, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
引用本文: 孙梦利, 刘枫飞, 杜鑫, 袁伟, 律鹏, 赵彦, 张冰焘, 张晓阳, 陈亮, 王铁山, 彭海波. γ辐照后硼硅酸盐玻璃的吸收光谱研究[J]. 原子核物理评论, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
SUN Mengli, LIU Fengfei, DU Xin, YUAN Wei, LV Peng, ZHAO Yan, ZHANG Bingtao, Zhang Xiaoyang, CHEN Liang, WANG Tieshan, PENG Haibo. Study on Absorption Spectra of Borosilicate Glasses Irradiated with γ Rays[J]. Nuclear Physics Review, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
Citation: SUN Mengli, LIU Fengfei, DU Xin, YUAN Wei, LV Peng, ZHAO Yan, ZHANG Bingtao, Zhang Xiaoyang, CHEN Liang, WANG Tieshan, PENG Haibo. Study on Absorption Spectra of Borosilicate Glasses Irradiated with γ Rays[J]. Nuclear Physics Review, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641

γ辐照后硼硅酸盐玻璃的吸收光谱研究

doi: 10.11804/NuclPhysRev.34.03.641
基金项目: 国家自然科学基金资助项目(11505085,11505084)
详细信息
    作者简介:

    孙梦利(1992-),女,江苏东海人,学士,从事粒子物理与原子核物理研究;E-mail:sunml15@lzu.edu.cn

    通讯作者: 彭海波,E-mail:penghb@lzu.edu.cn
  • 中图分类号: O482.1;O483

Study on Absorption Spectra of Borosilicate Glasses Irradiated with γ Rays

Funds: National Natural Science Foundation of China(11505085, 11505084)
More Information
    Corresponding author: 10.11804/NuclPhysRev.34.03.641
  • 摘要: 玻璃固化体是用来固化放射性废物的硅酸盐。作为放射性废物处理的第一道工程屏障,它的耐辐照性能尤其引人注目。本工作使用硼硅酸盐玻璃模拟玻璃固化体材料,用不同剂量的γ射线辐照硼硅酸盐玻璃模拟天然放射性对固化体的辐照损伤。通过测量和分析辐照后硼硅酸盐玻璃的吸收光谱,证实了辐照后在玻璃中产生了E'缺陷,非桥氧空位色心、过氧自由基以及过桥氧联接等缺陷。此外,还得出了不同微观结构随吸收剂量的演化关系。对于辐照后产生的缺陷,它们的浓度都随吸收剂量的增加而增大。同时,发现玻璃在辐照后其吸收光谱的带隙随着剂量的增加而逐渐变窄;而当吸收剂量大于等于105 Gy时,玻璃的带隙则达到饱和值。


    Vitrification is one kind of silicates which is used for immobilization of high-level waste (HLW). As the first engineered barrier of HLW disposition, its anti-irradiation characteristic is particularly noticeable. Vitrification is replaced by borosilicate glass to investigate radiation effect, and the irradiation damage generated by natural radioactivity in vitrification is simulated by different doses gamma rays on borosilicate glass. By measuring and analyzing the absorption spectrum of irradiated borosilicate glasses, it is confirmed that E'defect, non-bridging oxygen hole center, peroxy dangling bond and bridge oxygen link, etc. are induced in borosilicate glass after irradiation. Furthermore, the relations between the defects and absorbed doses are shown. For the concentrations of these defects induced by irradiation, all of them increase with absorbed dose. Meanwhile, absorption band gap in borosilicate glass after irradiation decreases with absorbed dose and the band gap becomes saturated when absorbed dose is equal to or greater than 105 Gy.
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    [3] YUAN Xiaoning, ZHANG Zhentao, CAI Xinan, et al. Atomic Energy Science and Technology, 2015, 49(2):240. (in Chinese) (袁晓宁, 张振涛, 蔡溪南, 等. 原子能科学技术, 2015, 49(2):240.)
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出版历程
  • 收稿日期:  2016-11-20
  • 修回日期:  2017-04-25
  • 刊出日期:  2017-07-18

γ辐照后硼硅酸盐玻璃的吸收光谱研究

doi: 10.11804/NuclPhysRev.34.03.641
    基金项目:  国家自然科学基金资助项目(11505085,11505084)
    作者简介:

    孙梦利(1992-),女,江苏东海人,学士,从事粒子物理与原子核物理研究;E-mail:sunml15@lzu.edu.cn

    通讯作者: 彭海波,E-mail:penghb@lzu.edu.cn
  • 中图分类号: O482.1;O483

摘要: 玻璃固化体是用来固化放射性废物的硅酸盐。作为放射性废物处理的第一道工程屏障,它的耐辐照性能尤其引人注目。本工作使用硼硅酸盐玻璃模拟玻璃固化体材料,用不同剂量的γ射线辐照硼硅酸盐玻璃模拟天然放射性对固化体的辐照损伤。通过测量和分析辐照后硼硅酸盐玻璃的吸收光谱,证实了辐照后在玻璃中产生了E'缺陷,非桥氧空位色心、过氧自由基以及过桥氧联接等缺陷。此外,还得出了不同微观结构随吸收剂量的演化关系。对于辐照后产生的缺陷,它们的浓度都随吸收剂量的增加而增大。同时,发现玻璃在辐照后其吸收光谱的带隙随着剂量的增加而逐渐变窄;而当吸收剂量大于等于105 Gy时,玻璃的带隙则达到饱和值。


Vitrification is one kind of silicates which is used for immobilization of high-level waste (HLW). As the first engineered barrier of HLW disposition, its anti-irradiation characteristic is particularly noticeable. Vitrification is replaced by borosilicate glass to investigate radiation effect, and the irradiation damage generated by natural radioactivity in vitrification is simulated by different doses gamma rays on borosilicate glass. By measuring and analyzing the absorption spectrum of irradiated borosilicate glasses, it is confirmed that E'defect, non-bridging oxygen hole center, peroxy dangling bond and bridge oxygen link, etc. are induced in borosilicate glass after irradiation. Furthermore, the relations between the defects and absorbed doses are shown. For the concentrations of these defects induced by irradiation, all of them increase with absorbed dose. Meanwhile, absorption band gap in borosilicate glass after irradiation decreases with absorbed dose and the band gap becomes saturated when absorbed dose is equal to or greater than 105 Gy.

English Abstract

孙梦利, 刘枫飞, 杜鑫, 袁伟, 律鹏, 赵彦, 张冰焘, 张晓阳, 陈亮, 王铁山, 彭海波. γ辐照后硼硅酸盐玻璃的吸收光谱研究[J]. 原子核物理评论, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
引用本文: 孙梦利, 刘枫飞, 杜鑫, 袁伟, 律鹏, 赵彦, 张冰焘, 张晓阳, 陈亮, 王铁山, 彭海波. γ辐照后硼硅酸盐玻璃的吸收光谱研究[J]. 原子核物理评论, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
SUN Mengli, LIU Fengfei, DU Xin, YUAN Wei, LV Peng, ZHAO Yan, ZHANG Bingtao, Zhang Xiaoyang, CHEN Liang, WANG Tieshan, PENG Haibo. Study on Absorption Spectra of Borosilicate Glasses Irradiated with γ Rays[J]. Nuclear Physics Review, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
Citation: SUN Mengli, LIU Fengfei, DU Xin, YUAN Wei, LV Peng, ZHAO Yan, ZHANG Bingtao, Zhang Xiaoyang, CHEN Liang, WANG Tieshan, PENG Haibo. Study on Absorption Spectra of Borosilicate Glasses Irradiated with γ Rays[J]. Nuclear Physics Review, 2017, 34(3): 641-645. doi: 10.11804/NuclPhysRev.34.03.641
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