Published 2011 | Version v1
Journal article

Evaluation of occupational exposure to naturally occurring radioactive materials in the Iranian ceramics industry

  • 1. Environmental Monitoring Section, National Radiation Protection Dept., Itanian Nuclear Regulatory Authority, Atomic Energy Organization of Iran AEOI, Tehran (Iran, Islamic Republic of)
  • 2. Dept. of Chemistry, Arak University, Arak (Iran, Islamic Republic of)

Description

Zircon contains small amounts of uranium, thorium and radium in its crystalline structure. The ceramic industry is one of the major consumers of zirconium compounds that are used as an ingredient at ∼10-20 % by weight in glaze. In this study, seven different ceramic factories have been investigated regarding the presence of radioactive elements with focus on natural radioactivity. The overall objective of this investigation is to provide information regarding the radiation exposure to workers in the ceramic industry due to naturally occurring radioactive materials. This objective is met by collecting existing radiological data specific to glaze production and generating new data from sampling activities. The sampling effort involves the whole process of glaze production. External exposures are monitored using a portable gamma-ray spectrometer and environmental thermoluminescence dosemeters, by placing them for 6 months in some workplaces. Internal routes of exposure (mainly inhalation) are studied using air sampling, and gross alpha and beta counting. Measurement of radon gas and its progeny is performed by continuous radon gas monitors that use pulse ionisation chambers. Natural radioactivity due to the presence of 238U, 232Th and 40K in zirconium compounds, glazes and other samples is measured by a gamma-ray spectrometry system with a high-purity germanium detector. The average concentrations of 238U and 232Th observed in the zirconium compounds are > 3300 and > 550 Bq kg-1, respectively. The specific activities of other samples are much lower than in zirconium compounds. The annual effective dose from external radiation had a mean value of ∼0.13 mSv y-1. Dust sampling revealed the greatest values in the process at the powdering site and hand weighing places. In these plants, the annual average effective dose from inhalation of long-lived airborne radionuclides was 0.226 mSv. 222Rn gas concentrations in the glaze production plant and storage warehouse were found to range from 10 to 213 Bq m-3. In this study, the estimated annual effective doses to exposed workers were < 1 mSv y-1. (authors)

Availability note (English)

Available from doi: http://dx.doi.org/10.1093/rpd/ncq441

Additional details

Identifiers

Publishing Information

Journal Title
Radiation Protection Dosimetry
Journal Volume
145
Journal Issue
4
Journal Page Range
p. 400-404
ISSN
0144-8420

Optional Information

Notes
6 refs