Characterization of the TE-NORM waste associated with oil and natural gas production in Abu Rudeis, Egypt

The present study was conducted to characterize the Technically Enhanced Naturally Occurring Radioactive Materials (TE-NORM) waste generated from oil and gas production. The waste was characterized by means of dry screening solid fractionation, X-ray analysis (XRF and XRD) and γ-ray spectrometry. Se...

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Veröffentlicht in:Journal of environmental radioactivity 2005, Vol.82 (1), p.7-19
Hauptverfasser: El Afifi, E.M., Awwad, N.S.
Format: Artikel
Sprache:eng
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Zusammenfassung:The present study was conducted to characterize the Technically Enhanced Naturally Occurring Radioactive Materials (TE-NORM) waste generated from oil and gas production. The waste was characterized by means of dry screening solid fractionation, X-ray analysis (XRF and XRD) and γ-ray spectrometry. Sediment of the TE-NORM waste was fractionated into ten fractions with particle sizes varying from less than 100 μm to more than 3 mm. The results showed that the TE-NORM waste contains mainly radionuclides of the 238U, 235U and 232Th series. The mean activity concentrations of 226Ra (of U-series), 228Ra (of Th-series) and 40K in the waste samples before fractionation (i.e. 3 mm) were found to amount to 68.9, 24 and 1.3 Bq/g (dry weight), respectively. After dry fractionation, the activity concentrations were widely distributed and enriched in certain fractions. This represented a 1.48 and 1.82-fold enrichment of 226Ra and 228Ra, respectively, in fraction F8 (2.0–2.5 mm) over those in bulk TE-NORM waste samples. The activity ratios of 238U/ 226Ra, 210Pb/ 226Ra, 223Ra/ 226Ra and 228Ra/ 224Ra were calculated and evaluated. Activity of the most hazardous radionuclide 226Ra was found to be higher than the exemption levels established by IAEA [International Atomic Energy Agency, 1994. International Basic Safety Standards for the Protection against Ionizing Radiation and for the Safety of Radiation Sources. GOV/2715/94, Vienna]. The radium equivalent activity (Ra-eq), radon ( 222Rn) emanation coefficient (EC) and absorbed dose rate ( D γr) were estimated and these are further discussed.
ISSN:0265-931X
1879-1700
DOI:10.1016/j.jenvrad.2004.11.001