Progress in Research and Development of Vitrification Technology for High-level Radioactive Liquid Waste at CIAE

被引:0
|
作者
Li Y. [1 ]
Zhang S. [1 ]
Xian L. [1 ]
Liu L. [1 ]
Tan S. [1 ]
Zhang H. [1 ]
Zhou H. [1 ]
Qie D. [1 ]
机构
[1] China Institute of Atomic Energy, Beijing
来源
Zhang, Shengdong (zhangsd@ciae.ac.cn) | 1600年 / Atomic Energy Press卷 / 54期
关键词
Cold crucible melter; High-level radioactive waste liquid; Joule-heated ceramic-lined melter; Vitrification;
D O I
10.7538/yzk.2020.zhuankan.0448
中图分类号
学科分类号
摘要
With the advancement of spent fuel reprocessing related projects, the demand for solidification of high-level radioactive liquid waste (HLLW) is also more urgent. The research progress of the vitrification of HLLW in equipment and material over the past forty years at China Institute of Atomic Energy (CIAE) was summarized in this paper. And based on the existing research, the future research and development priorities were analyzed and put forward, then the recommendations for the independent research and development of cold crucible melter and the localization of Joule-heated ceramic-lined melters (JHCMS) were made. © 2020, Editorial Board of Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:126 / 136
页数:10
相关论文
共 40 条
  • [21] CHOI K, KIM C W, PARK J K, Et al., Pilot-scale tests to vitrify Korean low-level wastes, WM'02 Conference, (2002)
  • [22] OJOVAN M I., Handbook of advanced radioactive waste conditioning technologies, (2011)
  • [23] YAN Jiade, SUN Liming, JING Weiguan, Et al., Level control inside pot for vitrification of simulated high-level wastes, Journal of Nuclear and Radiochemistry, 5, 1, pp. 45-49, (1983)
  • [24] 6, pp. 678-685, (1982)
  • [25] SHAO Fuyi, YAN Jiade, ZHANG Baoshan, Et al., Sulfate distribution in the pot type facility for vitrification of simulated sulfate, Atomic Energy Science and Technology, 24, 4, pp. 58-65, (1990)
  • [26] SHAO Fuyi, ZHANG Baoshan, SUN Liming, Et al., Design and verification test of a pilot plant for vitrification of simulated high-level liquid waste, Radiation Protection, 3, 1, pp. 26-32, (1998)
  • [27] pp. 389-393, (2015)
  • [28] (2001)
  • [29] LIU Lijun, QIE Dongsheng, ZHOU Hui, Et al., Verification experiment research of glass formulation for high sodium and high sulfur bearing HLLW, Journal of Nuclear and Radiochemistry, 36, 3, pp. 163-168, (2014)
  • [30] (2007)