Radiological Risk Assessment for French Silo at Al-Tuwaitha Nuclear Research Site
International Journal of Clinical Oncology and Cancer Research
Volume 2, Issue 5, October 2017, Pages: 99-105
Received: Jul. 8, 2017; Accepted: Jul. 21, 2017; Published: Sep. 7, 2017
Views 2048      Downloads 111
Authors
AL-Jasim Ali Kareem, Nuclear Safety Department, Ministry of Science & Technology, Baghdad, Iraq
Al-Draisawi Abbas Neamah, Nuclear Safety Department, Ministry of Science & Technology, Baghdad, Iraq
Al-Tameemi Nabeel Hashim, Nuclear Safety Department, Ministry of Science & Technology, Baghdad, Iraq
Article Tools
Follow on us
Abstract
The French silo is located at AL-Tuwaitha nuclear research site, it is intended for temporary storage of the radioactive waste with low half-life and low or medium radioactivity. The annual doses are calculated for workers in the silo and also the risk to injury with fated cancer. The concept of a source-related dose constraint was first introduced in International Commission on Radiological Protection (ICPR) publication 60. The idea was to provide a number that individual exposures from a single, specific source should not exceed, and below which optimization of protection should take place. Dose constraints were applied to occupational and public exposures from practices. The points survey (76 points inside the silo and 31 points outside the silo) were measured using the RadEye PRD device for 3 heights (0, 1 and 3m) for each point and the adoption of the height of 1 meter because it is the effective dose on the human. The highest annual dose rate inside the silo was obtained (33.41 mSv/y) at point (9,30) and the doses mean for all points was (2.0653mSv/y) within the range (0.06_33.41), and the highest reading for the risk to injury with cancer was (1.67E-3) at same point and the rate was (1E-4) within range (1.67E-3_17E-6), also the highest annual dose rate outside the silo was obtained (17.45 mSv/y) at point (25, 45) and the doses mean for all points was (0.867mSv/y) within the range (0.035-17.45), and the heights reading for the risk to injury with cancer was (9E-4) at same point and the rate was (4.34E-05) within range (1.73E-6_9E-4).
Keywords
Safety Assessment, Risk Assessment, Radiological Risk
To cite this article
AL-Jasim Ali Kareem, Al-Draisawi Abbas Neamah, Al-Tameemi Nabeel Hashim, Radiological Risk Assessment for French Silo at Al-Tuwaitha Nuclear Research Site, International Journal of Clinical Oncology and Cancer Research. Vol. 2, No. 5, 2017, pp. 99-105. doi: 10.11648/j.ijcocr.20170205.11
Copyright
Copyright © 2017 Authors retain the copyright of this article.
This article is an open access article distributed under the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0/) which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
References
[1]
INTERNATIONAL ATOMIC ENERGY AGENCY, Predisposal Management of Radioactive Waste, IAEA Safety Standards Series No. GSR Part 5, IAEA, Vienna (2009).
[2]
INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment for Facilities and Activities, IAEA Safety Standards Series No. GSR Part 4, IAEA, Vienna (2009).
[3]
INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Series No. 115, international basic safety standards for protection against ionizing radiation and for the safety of radiation sources, IAEA, Vienna (1996).
[4]
INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Report Series No.19, Generic models for use in assessing the impact of discharges radioactive substances to the environment, IAEA, Vienna (2001).
[5]
INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Series No. 111-F, The Principles of Radioactive Waste Management, IAEA, Vienna (1995).
[6]
NTERNATIONAL ATOMIC ENERGY AGENCY, Safety Series No. 111-G-1.1, Classification of Radioactive Waste, IAEA, Vienna (1994).
[7]
Al-Musawi, F., Shamsaldin, E. S. and Cochran, J. R., 2011, Radioactive Waste Management Challenges and Progress in Iraq,” Proceedings of the ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management ICEM2011, Reims, France.
[8]
Dennis, M. L., Shamsaldin, E. S. and Cochran, J. R., 2011, Iraq Liquid Radioactive Waste Tanks Maintenance and Monitoring Program Plan, SAND2011-6549, Sandia National Laboratories, Albuquerque, NM.
[9]
http://www-ns.iaea.org/projects/iraq/tuwaitha.asp?s=8&l=66.
[10]
http://www-ns.iaea.org/projects/iraq/sites-overview.asp?s=8&l=66.
[11]
Thermo scientific, Manual of Alarming Personal Radiation Detector, Rad Eye PRD, DB_057-050322 E.
[12]
INTERNATIONAL ATOMIC ENERGY AGENCY, Specific Safety Requirements No. SSR-5, Disposal of Radioactive Waste, IAEA, Vienna (2011).
[13]
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, The 2007 Recommendations of the International Commission on Radiological Protection, Publication 103, Pergamon Press, ICRP, Oxford and New York (2007).
[14]
Dr. Ann Mc Garry, Dose Constraints in Occupational Radiation Protection, Regulations and Practices, Radiological Protection Institute of Ireland Chair.
[15]
INTERNATIONAL COMMISSION ON RADIOLOGICAL PROTECTION, Publication 60, 1990 Recommendations of the International Commission on Radiological Protection, Annals ICRP 21 (1-3): 1-201, 1991.
ADDRESS
Science Publishing Group
1 Rockefeller Plaza,
10th and 11th Floors,
New York, NY 10020
U.S.A.
Tel: (001)347-983-5186