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Treatment of Radiological Medical Waste Using Concrete Cubic Molds

Received: 8 September 2018     Accepted: 15 October 2018     Published: 13 November 2018
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Abstract

Concrete cubic molds were made and manufactured using a fixed percentage of cement and sand to be as a container for the radiological medical waste in order to prevent radiation during the transfer of radioactive waste from hospitals to their own landfill sites to preserve the safety of people and the environment from radiation pollution. The maximum dose rate was 173.744 µSv/h in NHTc2 sample measured using RAD EYE B20 dosimeter, which has a very high activity as a medical waste (28.568 µCi), while the lowest dose value 0.297 µSv/h and activity 0.041 µCi was for MCI4 sample, except the dead samples which less than detection limit for the NaI(Tl) system. Also, the efficiency calculations of manufactured molds with thickness 3 cm were done by using Ba-133 and Cs-137 as a point source, because of the energies of these sources are close to that for I-131 and Tc-99 m exist in the medical waste samples. The shielding percentages were calculated and have very high values with using concrete molds, and the dose rate decreases with increasing the sand in the mold. Measurement of resistivity to compression for the molds were done to acknowledgment the strength to hold radiological waste through transfers or store of these kinds of waste. We found that the increase of the cement percentage (chosen 10, 20 and 30%) leads to increasing the mold strength.

Published in American Journal of Nanosciences (Volume 4, Issue 3)
DOI 10.11648/j.ajn.20180403.12
Page(s) 35-39
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

Keywords

Radiological Medical Waste, Concrete Molds, Dose Rate, NaI(Tl), Rad Eye B20

References
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[2] Samarin, A., Use of Concrete as a Biological Shield from Ionizing Radiation, Energy and Environmental Engineering, 1(2), pp. 90-97, 2013.
[3] Batten, A. W. C., Effects of Irradiation on the Strength of Concrete, United Kingdom Atomic Energy Authority, Harwell, 1960.
[4] Alexander, S. C., Effects of irradiation on concrete: final results. K. Harvell, U. K. Atomic Energy Research Establishment, 1963.
[5] Abulfaraj, W. H, and Kamal, S, M, “Evaluation of Ilmenite Serpentine Concrete and Ordinary Concrete as Nuclear Reactor Shielding”, Radiation Physics and Chemistry, Elsevier Science Ltd., 44(1/ 2), pp. 139-148, 1994.
[6] Branson BM, Sodd V J, Nishiyama H, et al. Use of syringe shields in clinical practice. Clinical Nuc. Med., 1: 56-59, 1976.
[7] Burr JE, Berg R. Radiation dose to hands from radiopharmaceuticals- Preparation versus injections. J Nuc. Med. Technol., 5: 158-60, 1977.
[8] Ahmed S. N., "Physics and Engineering of Radiation Detection", 1 st edition, Academic Press Inc. Published by Elsevier, Printed and bound in Great Britain, pp. 1-235 2007.
[9] Driver I, Packer S. Radioactive waste discharge quantities for patients undergoing radioactive iodine therapy for thyroid carcinoma. Nucl Med Comm. 2001; 22:1129–32. [PubMed]
[10] Leung PM, Nikolic M. Disposal of therapeutic 131-I waste using a multiple holding tank system. Health Phys. 1998; 10:315–21. [PubMed]
[11] Ravichandran R, Pant GS. Storage and disposal of radioactive waste. In: Pant GS, editor. Radiation Safety of Unsealed Sources. 2 nd ed. Mumbai: Himalaya Pub. Co; 2000. pp. 237–48.
[12] Ravichandran R. Storage and disposal of radioactive waste. In: Pant GS, editor. Radiation safety for unsealed sources. 1 nd ed. Mumbai: Himalaya Pub. Co; 1998. pp. 102–14.
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[15] Thayalan K, editor. Radioactive waste disposal. In Text Book of Radiological Safety. Chennai: Jaypee Med Publication; 2010. p. 267. p. 88.
[16] Applying radiation safety standards in Nuclear Medicine. Safety Reports Series No.40. Vienna: IAEA; 2005.
Cite This Article
  • APA Style

    Ali Abdulwahab Ridha, Lara Adnan Kadhim, Basim Abdlsattar Hussain. (2018). Treatment of Radiological Medical Waste Using Concrete Cubic Molds. American Journal of Nanosciences, 4(3), 35-39. https://doi.org/10.11648/j.ajn.20180403.12

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    ACS Style

    Ali Abdulwahab Ridha; Lara Adnan Kadhim; Basim Abdlsattar Hussain. Treatment of Radiological Medical Waste Using Concrete Cubic Molds. Am. J. Nanosci. 2018, 4(3), 35-39. doi: 10.11648/j.ajn.20180403.12

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    AMA Style

    Ali Abdulwahab Ridha, Lara Adnan Kadhim, Basim Abdlsattar Hussain. Treatment of Radiological Medical Waste Using Concrete Cubic Molds. Am J Nanosci. 2018;4(3):35-39. doi: 10.11648/j.ajn.20180403.12

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  • @article{10.11648/j.ajn.20180403.12,
      author = {Ali Abdulwahab Ridha and Lara Adnan Kadhim and Basim Abdlsattar Hussain},
      title = {Treatment of Radiological Medical Waste Using Concrete Cubic Molds},
      journal = {American Journal of Nanosciences},
      volume = {4},
      number = {3},
      pages = {35-39},
      doi = {10.11648/j.ajn.20180403.12},
      url = {https://doi.org/10.11648/j.ajn.20180403.12},
      eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ajn.20180403.12},
      abstract = {Concrete cubic molds were made and manufactured using a fixed percentage of cement and sand to be as a container for the radiological medical waste in order to prevent radiation during the transfer of radioactive waste from hospitals to their own landfill sites to preserve the safety of people and the environment from radiation pollution. The maximum dose rate was 173.744 µSv/h in NHTc2 sample measured using RAD EYE B20 dosimeter, which has a very high activity as a medical waste (28.568 µCi), while the lowest dose value 0.297 µSv/h and activity 0.041 µCi was for MCI4 sample, except the dead samples which less than detection limit for the NaI(Tl) system. Also, the efficiency calculations of manufactured molds with thickness 3 cm were done by using Ba-133 and Cs-137 as a point source, because of the energies of these sources are close to that for I-131 and Tc-99 m exist in the medical waste samples. The shielding percentages were calculated and have very high values with using concrete molds, and the dose rate decreases with increasing the sand in the mold. Measurement of resistivity to compression for the molds were done to acknowledgment the strength to hold radiological waste through transfers or store of these kinds of waste. We found that the increase of the cement percentage (chosen 10, 20 and 30%) leads to increasing the mold strength.},
     year = {2018}
    }
    

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  • TY  - JOUR
    T1  - Treatment of Radiological Medical Waste Using Concrete Cubic Molds
    AU  - Ali Abdulwahab Ridha
    AU  - Lara Adnan Kadhim
    AU  - Basim Abdlsattar Hussain
    Y1  - 2018/11/13
    PY  - 2018
    N1  - https://doi.org/10.11648/j.ajn.20180403.12
    DO  - 10.11648/j.ajn.20180403.12
    T2  - American Journal of Nanosciences
    JF  - American Journal of Nanosciences
    JO  - American Journal of Nanosciences
    SP  - 35
    EP  - 39
    PB  - Science Publishing Group
    SN  - 2575-4858
    UR  - https://doi.org/10.11648/j.ajn.20180403.12
    AB  - Concrete cubic molds were made and manufactured using a fixed percentage of cement and sand to be as a container for the radiological medical waste in order to prevent radiation during the transfer of radioactive waste from hospitals to their own landfill sites to preserve the safety of people and the environment from radiation pollution. The maximum dose rate was 173.744 µSv/h in NHTc2 sample measured using RAD EYE B20 dosimeter, which has a very high activity as a medical waste (28.568 µCi), while the lowest dose value 0.297 µSv/h and activity 0.041 µCi was for MCI4 sample, except the dead samples which less than detection limit for the NaI(Tl) system. Also, the efficiency calculations of manufactured molds with thickness 3 cm were done by using Ba-133 and Cs-137 as a point source, because of the energies of these sources are close to that for I-131 and Tc-99 m exist in the medical waste samples. The shielding percentages were calculated and have very high values with using concrete molds, and the dose rate decreases with increasing the sand in the mold. Measurement of resistivity to compression for the molds were done to acknowledgment the strength to hold radiological waste through transfers or store of these kinds of waste. We found that the increase of the cement percentage (chosen 10, 20 and 30%) leads to increasing the mold strength.
    VL  - 4
    IS  - 3
    ER  - 

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Author Information
  • Physics Department, College of Science, Mustansiriyah University, Baghdad, Iraq

  • Physics Department, College of Science, Mustansiriyah University, Baghdad, Iraq

  • Ministry of Science and Technology, Directorate of Hazardous Wastes, Baghdad, Iraq

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