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 |
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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. |
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ISSN: | 0265-931X 1879-1700 |
DOI: | 10.1016/j.jenvrad.2004.11.001 |