Elemental behaviors of ?-irradiated borosilicate glass as a vitrification model

被引:3
|
作者
Zhang, Jiandong [1 ]
Xia, Xiaoyu [1 ]
Zeng, Fanrong [1 ]
Xi, Xiaochong [1 ]
Zhang, Xiaoyang [2 ]
Pan, Yuhe [2 ]
Sun, Yuxi [2 ]
Jia, Wenbao [1 ]
Peng, Haibo [2 ]
机构
[1] Nanjing Univ Aeronaut & Astronaut, Coll Mat Sci & Technol, Nanjing 210000, Peoples R China
[2] Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China
基金
中国国家自然科学基金;
关键词
borosilicate glass; electron microscopy; ion-exchange; gamma-irradiation; NUCLEAR-WASTE GLASS; ALTERATION LAYERS; RADIATION-DAMAGE; TOF-SIMS; SODIUM; ELECTRON; CORROSION; MECHANISM;
D O I
10.1111/ijag.16632
中图分类号
TQ174 [陶瓷工业]; TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Borosilicate glass has been extensively studied due to its unique properties of solidifying high-level radioactive waste (HLW). However, the responses of borosilicate glass under ? irradiation are not fully understood. In this work, NBS9 and NBS10 glass were irradiated by ?-rays at absorbed doses of 8 kGy and 800 kGy, respectively. Scanning electronic microscopy, energy dispersive X-ray, and time-of-flight secondary ion mass spectrometry (ToF-SIMS) were used to observe the surface morphology and elemental distributions. The results show that the borosilicate glass remains stable until the absorbed dose was up to 800 kGy. At 800 kGy, the samples precipitate particles composed of Na and O on the surface. Na and B near the surface are significantly reduced under ?-rays irradiation. The results indicate that the effects of ? irradiation on glass vitrification are obvious with certain accumulated doses. The changes of glass structures and elemental distributions by ?-ray irradiation are also dependent on glass compositions.
引用
收藏
页码:380 / 388
页数:9
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