There has been great concern about the health risks associated with exposure to radioactivity present in soil, thus in this present study, absorbed dose rate measurements were carried out at some selected samples of contaminated soil. The purpose is to examine to what extent such measurements can be used to delineate the effect radiation to the workers and to assess the radiation risk of radioactive waste management personnel by calculating the annual dose of external radiation exposure and the amount of radioactive dose absorbed by the workers. Ladlum detector used to measure the exposure dose rate (µR/h). The germanium system was used to analyze the samples collected from the decontamination processes, the activity concentration ranged from (1026.21 to 25961.5) Bq/kg. The value of the annual dos rate vary between (5.55E-05 to.40E-03) Sv/h.
Published in | American Journal of Mechanics and Applications (Volume 6, Issue 1) |
DOI | 10.11648/j.ajma.20180601.15 |
Page(s) | 23-26 |
Creative Commons |
This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited. |
Copyright |
Copyright © The Author(s), 2018. Published by Science Publishing Group |
External Dose Rate, Absorbed Dose Rate, Activity Concentration
[1] | International Commission on Radiological Protection, Annals of the ICRP (Feb 23, 2012), Occupational Intakes of Radionuclides, Part 1. |
[2] | International Atomic Energy Agency, Iaea-Tecdoc-1817, Selection of Technical Solutions for The Management of Radioactive Waste, TECDOC-1817, Vienna, 2017. |
[3] | Emad S. Shamsaldin, Asia H. Al-Mashhadani and Saad M. Abd (2014), Risk assessment for retrieving legacy radioactive waste in Al-Tuwaitha site, Advances in Applied Science Research, 5 (5):29-38. |
[4] | International Atomic Energy Agency (IAEA), "Measurement of Radionuclides in Food and the Environment". Technical Report Series No. 295, Vienna: IAEA Publication, VIENNA, 1989. |
[5] | Canberra, USA, Enhanced Capability ultra-light. Portable Ha-Held Radioisotope Identifier. |
[6] | Odolfo Avila, Facilia AB, Methodology for calculation ofdoses to man and mplementation in Pandora, Ulla Bergström, Swepro Project Management AB, ISSN 1402-3091 SKB Rapport R-06-68, July 2006. |
[7] | Eckerman and Legget 1996. |
[8] | Glenn F. Knoll, Radiation Detection and Measurement, Fourth Edition, Wiley, 2010. |
[9] | James E. Turner, Atoms, Radiation, and Radiation Protection, Third, Completely Revised and Enlarged Edition, ISBN 978-3-527-40606-7, USA.2007. |
[10] | International Commission on Radiological Protection. The 2007 Recommendations of the International Commission on Radiological Protection. Annals of the ICRP 37 (2-4). ICRP Publication 103. Pergamon Press, Oxford, 2007. |
[11] | National Council on Radiation Protection and Measurements (NCRP), Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 160 U.S. NCRP, Washington D. C. 2009. |
APA Style
Saad Mohammed Abd, Taha Yaseen Mansoor, Hussein Saady Al-Daffaie. (2018). Determination of Absorbed Dose Results from Radioactive Waste Sampling and Assay. American Journal of Mechanics and Applications, 6(1), 23-26. https://doi.org/10.11648/j.ajma.20180601.15
ACS Style
Saad Mohammed Abd; Taha Yaseen Mansoor; Hussein Saady Al-Daffaie. Determination of Absorbed Dose Results from Radioactive Waste Sampling and Assay. Am. J. Mech. Appl. 2018, 6(1), 23-26. doi: 10.11648/j.ajma.20180601.15
AMA Style
Saad Mohammed Abd, Taha Yaseen Mansoor, Hussein Saady Al-Daffaie. Determination of Absorbed Dose Results from Radioactive Waste Sampling and Assay. Am J Mech Appl. 2018;6(1):23-26. doi: 10.11648/j.ajma.20180601.15
@article{10.11648/j.ajma.20180601.15, author = {Saad Mohammed Abd and Taha Yaseen Mansoor and Hussein Saady Al-Daffaie}, title = {Determination of Absorbed Dose Results from Radioactive Waste Sampling and Assay}, journal = {American Journal of Mechanics and Applications}, volume = {6}, number = {1}, pages = {23-26}, doi = {10.11648/j.ajma.20180601.15}, url = {https://doi.org/10.11648/j.ajma.20180601.15}, eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ajma.20180601.15}, abstract = {There has been great concern about the health risks associated with exposure to radioactivity present in soil, thus in this present study, absorbed dose rate measurements were carried out at some selected samples of contaminated soil. The purpose is to examine to what extent such measurements can be used to delineate the effect radiation to the workers and to assess the radiation risk of radioactive waste management personnel by calculating the annual dose of external radiation exposure and the amount of radioactive dose absorbed by the workers. Ladlum detector used to measure the exposure dose rate (µR/h). The germanium system was used to analyze the samples collected from the decontamination processes, the activity concentration ranged from (1026.21 to 25961.5) Bq/kg. The value of the annual dos rate vary between (5.55E-05 to.40E-03) Sv/h.}, year = {2018} }
TY - JOUR T1 - Determination of Absorbed Dose Results from Radioactive Waste Sampling and Assay AU - Saad Mohammed Abd AU - Taha Yaseen Mansoor AU - Hussein Saady Al-Daffaie Y1 - 2018/03/23 PY - 2018 N1 - https://doi.org/10.11648/j.ajma.20180601.15 DO - 10.11648/j.ajma.20180601.15 T2 - American Journal of Mechanics and Applications JF - American Journal of Mechanics and Applications JO - American Journal of Mechanics and Applications SP - 23 EP - 26 PB - Science Publishing Group SN - 2376-6131 UR - https://doi.org/10.11648/j.ajma.20180601.15 AB - There has been great concern about the health risks associated with exposure to radioactivity present in soil, thus in this present study, absorbed dose rate measurements were carried out at some selected samples of contaminated soil. The purpose is to examine to what extent such measurements can be used to delineate the effect radiation to the workers and to assess the radiation risk of radioactive waste management personnel by calculating the annual dose of external radiation exposure and the amount of radioactive dose absorbed by the workers. Ladlum detector used to measure the exposure dose rate (µR/h). The germanium system was used to analyze the samples collected from the decontamination processes, the activity concentration ranged from (1026.21 to 25961.5) Bq/kg. The value of the annual dos rate vary between (5.55E-05 to.40E-03) Sv/h. VL - 6 IS - 1 ER -