![Characterization of the TE-NORM waste associated with oil and natural gas production in Abu Rudeis, Egypt [An article from: Journal of Environmental Radioactivity]](https://www.ebooknetworking.net/books/noimage.jpg)
Characterization of the TE-NORM waste associated with oil and natural gas production in Abu Rudeis, Egypt [An article from: Journal of Environmental Radioactivity]
Book Details
Author(s)E.M. El Afifi, N.S. Awwad
PublisherElsevier
ISBN / ASINB000RR3SFK
ISBN-13978B000RR3SF3
AvailabilityAvailable for download now
Sales Rank10,640,056
MarketplaceUnited States 🇺🇸
Description
This digital document is a journal article from Journal of Environmental Radioactivity, published by Elsevier in 2005. The article is delivered in HTML format and is available in your Amazon.com Media Library immediately after purchase. You can view it with any web browser.
Description:
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 @c-ray spectrometry. Sediment of the TE-NORM waste was fractionated into ten fractions with particle sizes varying from less than 100@mm to more than 3mm. The results showed that the TE-NORM waste contains mainly radionuclides of the ^2^3^8U, ^2^3^5U and ^2^3^2Th series. The mean activity concentrations of ^2^2^6Ra (of U-series), ^2^2^8Ra (of Th-series) and ^4^0K in the waste samples before fractionation (i.e. 3mm) were found to amount to 68.9, 24 and 1.3Bq/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 ^2^2^6Ra and ^2^2^8Ra, respectively, in fraction F8 (2.0-2.5mm) over those in bulk TE-NORM waste samples. The activity ratios of ^2^3^8U/^2^2^6Ra, ^2^1^0Pb/^2^2^6Ra, ^2^2^3Ra/^2^2^6Ra and ^2^2^8Ra/^2^2^4Ra were calculated and evaluated. Activity of the most hazardous radionuclide ^2^2^6Ra 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 (^2^2^2Rn) emanation coefficient (EC) and absorbed dose rate (D"@c"r) were estimated and these are further discussed.
Description:
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 @c-ray spectrometry. Sediment of the TE-NORM waste was fractionated into ten fractions with particle sizes varying from less than 100@mm to more than 3mm. The results showed that the TE-NORM waste contains mainly radionuclides of the ^2^3^8U, ^2^3^5U and ^2^3^2Th series. The mean activity concentrations of ^2^2^6Ra (of U-series), ^2^2^8Ra (of Th-series) and ^4^0K in the waste samples before fractionation (i.e. 3mm) were found to amount to 68.9, 24 and 1.3Bq/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 ^2^2^6Ra and ^2^2^8Ra, respectively, in fraction F8 (2.0-2.5mm) over those in bulk TE-NORM waste samples. The activity ratios of ^2^3^8U/^2^2^6Ra, ^2^1^0Pb/^2^2^6Ra, ^2^2^3Ra/^2^2^6Ra and ^2^2^8Ra/^2^2^4Ra were calculated and evaluated. Activity of the most hazardous radionuclide ^2^2^6Ra 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 (^2^2^2Rn) emanation coefficient (EC) and absorbed dose rate (D"@c"r) were estimated and these are further discussed.
