RADIATION PROTECTION ›› 2023, Vol. 43 ›› Issue (1): 17-30.

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Solubility of typical PGMs in HLLW glass and influence of PGMs on the properties of HLLW glass

LU Jiawei1, LIN Peng2, LI Lili2, ZHAO Xing1, WANG Yi1, WENG Hanqin1, LIN Mingzhang1   

  1. 1. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027;
    2. China Nuclear Power Technology Research Institute Co. LTD., Guangdong Shenzhen 518026
  • Received:2021-11-17 Online:2023-01-20 Published:2023-03-20

Abstract: This paper mainly summarized the chemical behaviors (the content and the existing form) of precious metals (PGMs) in high-level liquid radioactive waste (HLLW) and the solubility, the existing form and the granularity of PGMs in HLLW glass. At the same time, the influence of PGMs on the properties of HLLW glass (rheology, viscosity, thermal conductivity and resistance) was summarized. The results were expected to provide a research basis for the solubility, the chemical behavior and sediment mechanism of typical PGMs in HLLW glass. Besides, The results were hopeful to provide a theoretical basis for studying the influence of typical PGMs on the properties of HLLW glass.

Key words: precious metal, high-level liquid radioactive waste, vitrification, solubility, properties of glass

CLC Number: 

  • TL941+.113