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Radiological characterization of the irt-5000(14-Tammuz) research nuclear reactor at Al-Tuwaitha nuclear center in Iraq

  • Iman Tarik Al-AlawyEmail author
  • Osama Abdulameer Mzher
Original Article
  • 65 Downloads

Abstract

Measurements were made at the destroyed nuclear reactor IRT-5000 (14-Tammuz research nuclear reactor at AL-Tuwaitha Nuclear Center in Iraq) to provide a basic comprehensive radiological characterization and to assess risk and dose for the workers in the workplace. Samples were collected from the site and analyzed, as well as using a portable survey meter to determine the external exposure dose rates. The quantity and quality of radionuclides were determined using gamma spectrometry techniques. The dose rate measured within the reactor core body ranged from 55 to 1250 mSv/h. The maximum dose was recorded in the middle of the corner near the horizontal experimental channel number seven, with activity concentration of 19.97 GBq estimated from Co-60 isotope. Most samples were contaminated with Cs-137, Co-60, and Eu-152 isotopes. The highest activity concentration of Cs-137 is 14772.41 ± 99.91 Bq/L and Co-60 is 7642.22 ± 40.02 Bq/kg, were found in slag from reactor tank. Two scenarios were developed based on the water level of the reactor tank. Assuming there are three locations for workers on the reactor surface. The annual dose of workers on the surface of the reactor (when the reactor tank is empty) ranges from 116 to 153 mSv, which is higher than the annual dose limit for workers. Therefore, workers will be subjected to the principle of As Low As Reasonable Achievable (ALARA) during all phases of dismantling nuclear reactor IRT-5000 (14-Tammuz) as recommended by International Atomic Energy Agency (IAEA).

Keywords

Radiological characterization Risk assessment Dose rate IRT-5000 reactor 

Notes

Acknowledgements

The authors wish to thank AL-Tuwaitha Nuclear Center in Iraq, to provide administrative facilities in the implementation of this study. Great thanks to Mustansiriyah University, Baghdad, Iraq for providing scientific assistance to carry out this research work.

References

  1. Abramidze SHP, Katamadze NM, Kiknadze GG, Saralidze ZK (2000) Decommissioning of the research nuclear reactor IRT-M and problems connected with radioactive waste. IAEA-CN-78 52:214–218Google Scholar
  2. Canberra (2016) STTC wide range gamma probe (C57968). Mirion Technologies, US. http://www.canberra.com/products/hp_radioprotection/pdf/STTC-SS-C47968.pdf
  3. Canberra (2017a) User’s manuel for MIP 10 digital desktop dose rate and survey meter (C39173). Mirion Technologies, US. http://www.canberra.com/products/hp_radioprotection/pdf/MIP-10-Digital-SS-C39173.pdf
  4. Canberra (2017b) Model S573 ISOCS*™ Calibration Software (C40166). Mirion Technologies, U.S. http://www.canberra.com/products/insitu_systems/pdf/ISOCS-SS-C40166.pdf
  5. Cember H, Johnson TE (2009) Introduction to healthy physics, 4th edn. McGraw-Hill, New York, pp 224–226Google Scholar
  6. Chesser RK, Rodgers BE, Bondarkov M, Shubber E, Phillips CJ (2009) Piecing together Iraq’s nuclear legacy. Bull Atomic Sci 65(3):19–33.  https://doi.org/10.2968/065003004 CrossRefGoogle Scholar
  7. Cochran J, Danneels J, Phillips CJ, Chesser RK (2006) Iraq nuclear facility dismantlement and disposal project. Sandia National Laboratories Voice 505-844-5256Google Scholar
  8. Holden NE, Reciniello RN, Hu JP (2004) Radiological characterization of the pressure vessel internals of the BNL high flux beam reactor. Health Phys 87(2 suppl):S25–S30CrossRefGoogle Scholar
  9. Hulubei H (2012) Decommissioning of the VVR-S research reactor—radiological characterization of the reactor block. Rom Rep Phys 64(2):387–398Google Scholar
  10. IAEA (1997) Characterization of radioactive waste forms and packages, Technical Report Series No. 383.STI/DOC/010/383; (ISBN: 92-0-100497-4). IAEA, ViennaGoogle Scholar
  11. IAEA (1998) Radiological characterization of shut down nuclear reactors for decommissioning purposes, Technical Report Series No. 389. IAEA, ViennaGoogle Scholar
  12. IAEA (1999) On-site disposal as a decommissioning strategy, TECDOC-1124. IAEA, Vienna, ISSN 1011–4289Google Scholar
  13. IAEA (2006) Decommissioning of facilities using radioactive material. In: Requirement S Safety standards for protecting people and the environment, GSR Part 6. Series No. WS-R- 5. IAEA, ViennaGoogle Scholar
  14. IAEA (2007) Strategy and methodology for radioactive waste characterization. TECDOC-1537, ISBN 92-0-100207–6 ISSN 1011–4289, Vienna, IAEAGoogle Scholar
  15. Jeong KS, Choi BS, Moon JK (2014) Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities. Ann Nucl Energy 73:441–445.  https://doi.org/10.1016/j.anucene.2014.07.027 CrossRefGoogle Scholar
  16. Lloyd NS, Chenery SRN, Parrish RR (2009) The distribution of depleted uranium contamination in Colonie, NY, USA. Sci Total Environ 408:(2009) 397–407.  https://doi.org/10.1016/j.scitotenv.2009.09.024 CrossRefGoogle Scholar
  17. Mikhalevich A (2000) Decommissioning of Research Reactor: Problems and Experience. Knoxville, TN. https://pdfs.semanticscholar.org/e00a/3b1a79a5d5b015c12ad8bd9ba2663897acea.pdf
  18. Nonova TZ, Stankov D, Mladenov AL, Krezhov K (2014) Radiological characterization activities during the partial dismantling of the IRT—sofia research reactor facilities. Rom J Phys 59(9–10):976–988Google Scholar
  19. Nuccetelli C, Trevisi R, Leonardi F, Ampollini M, Cardellini F, Tonnarini S, Kovler K (2017) Radiological characterization of the ancient Roman tuff-pozzolana underground quarry in Orvieto (Italy): a natural laboratory to revisit the interactions between radionuclides and aerosols. J Environ Radioact 168:54–60.  https://doi.org/10.1016/j.jenvrad.2016.07.003 CrossRefGoogle Scholar
  20. ORTEC (2014) Micro-detective-HX enhanced capability, ultra-light. High-Fidelity Hand-Held Radioisotope Identifier, USGoogle Scholar
  21. UNSCEAR (2000) Sources and effects of ionizing radiation. Report to general assembly, with scientific annexes. United Nations, New YorkGoogle Scholar
  22. Venkataraman R, Bronson F, Abshevich V, Young BM, Field M (1999) Validation of in situ object counting system (ISOCS) mathematical efficiency calibration software. Nucl Instrum Methods Phys Res Sect A 422(1–3): 450–454.  https://doi.org/10.1016/S0168-9002(98)01115-2 CrossRefGoogle Scholar
  23. Yu C, Le Poire DJ, Cheng JJ (2003) User’s manual for RESRAD-BUILD version 3. Environmental Assessment Division Argonne National Laboratory, USCrossRefGoogle Scholar

Copyright information

© Springer-Verlag GmbH Germany, part of Springer Nature 2019

Authors and Affiliations

  1. 1.Physics Department, College of ScienceMustansiriyah UniversityBaghdadIraq
  2. 2.Directorates of Radioactive Waste Treatments and ManagementMinistry of Science and TechnologyBaghdadIraq

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