Radionuclide transport and radiation protection in production process of ZrOCl₂ from zircon sand in a factory

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 relevant measures for radiation protection are suggested. (authors)