RADIATION PROTECTION ›› 2018, Vol. 38 ›› Issue (4): 293-299.

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Radionuclide transport and radiation protection in production process ofZrOCl2 from zircon sand in a factory

GUO Qingli, WANG Yan, LI Xianjie   

  1. Beijing Research Institute of Chemical Engineering and Metallurgy, Beijing 101149
  • Received:2017-08-15 Online:2018-07-20 Published:2020-07-28

Abstract: Radionuclide transport and radiation protection are discussed based on analysis of some natural radionuclides in feedstocks, products, intermediates, and wastes in the production process of zirconium oxychloride (ZrOCl2) from zircon sand in a factory. The results showed that U, Th, and 226Ra were enriched in the third waste acid with concentrations of 1.52 g/L, 1.31 g/L, and 801 Bq/L, respectively. 86% of U and 99% of Th went into final residues of waste water treatment, 14% of U was discharged into treated waste water. Natural radionuclides in ZrOCl2 are too little and no attention is needed. The residues from the ZrOCl2 production process need to be treated as radioactive wastes. The additional external irradiation doses of workers are calculated as a maximum of 1.61 mSv/a. The relavant measures for radiation protection are suggested.

Key words: zircon sand, zirconium oxychloride, radioactivity, waste acid

CLC Number: 

  • TL75+1