DOI QR코드

DOI QR Code

A study on characteristics and internal exposure evaluation of radioactive aerosols during pipe cutting in decommissioning of nuclear power plant

  • Kim, Sun Il (Department of Nuclear Engineering, Chosun University) ;
  • Lee, Hak Yun (Department of Nuclear Engineering, Chosun University) ;
  • Song, Jong Soon (Department of Nuclear Engineering, Chosun University)
  • Received : 2017.11.10
  • Accepted : 2018.06.11
  • Published : 2018.10.25

Abstract

Kori unit #1, which is the first commercial nuclear power plant in Korea, was permanently shutdown in June 2017, and it is about to be decommissioned. Currently in Korea, researches on the decommissioning technology are actively conducted, but there are few researches on workers internal exposure to radioactive aerosol that is generated in the process of decommissioning nuclear power plants. As a result, the over-exposure of decommissioning workers is feared, and the optimal working time needs to be revised in consideration of radioactive aerosol. This study investigated the annual exposure limits of various countries, which can be used as an indicator in evaluating workers' internal exposure to radioactive aerosol during pipe cutting in the process of decommissioning nuclear power plants, and the growth and dynamics of aerosol. Also, to evaluate it, the authors compared/analyzed the cases of aerosol generated when activated pipes are cut in the process of nuclear power plants and the codes for evaluating internal exposure. The evaluation codes and analyzed data conform to ALARA, and they are believed to be used as an important indicator in deriving an optimal working time that does not excess the annual exposure limit.

Keywords

References

  1. M.Y. Kim, S.H. Park, Characteristics of radioactive aerosol particles in nuclear power plant containments, Particle Aerosol Res. (2014).
  2. H.-J. Allelein, et al., State of the Art Report on Nuclear Aerosols, Organization for Economic Cooperation and development of Nuclear Energy Agency, Committee on the safety of nuclear installations, NEA/CSNI, 2009.
  3. P. Worth Longest, Landon T. Holbrook, In silico models aerosol delivery to the respiratory tract - development and applications, Adv. Drug Deliv. Rev. (2011) 16. ADR-12134.
  4. Pascal Demoly, Paul Hagedoorn, Anne H. de Boer, Henderik W. Frijlink, The clinical relevance of dry powder inhaler performance for drug delivery, Respir. Med. 108 (2014) 1195-1203, 2014. https://doi.org/10.1016/j.rmed.2014.05.009
  5. J.W. Eom, B. Lee, Analytical methods for atmospheric particulate aerosols: focused on the physical properties and chemical composition of metals and water soluble ionic compounds, Analytical Sci. Technol. 28 (3) (2015) 139-159. https://doi.org/10.5806/AST.2015.28.3.139
  6. OECD/NEA, R&D and Innovation Needs for Decommissioning Nuclear Facilities, OECD/NEA, Paris, 2014.
  7. Stefan Mundigl, The New Euratom Basic Safety Standard Directive, European Commission - Directorate General for Energy - Directorate Nuclear Safety and Fuel Cycle - Radiation Protection Unit, 2014.
  8. Vienna, Summary of the European Directive 2013/59/Euratom: Essentials for Health Professionals in Radiology, European Society of Radiology(ESR), 2015.
  9. U.S.NRC, Subpart C-occupational Dose Limits, 1991, 56 FR 23396.
  10. NSSC, Nuclear Safety Commission Notice No. 2011-29, 2011.
  11. Ministry of Health, Labour and Welfare, Opinions on the Draft Ministerial Ordinance to Revise Part of the Ordinance on Prevention of Ionizing Radiation Hazards, 2015.
  12. Chaim Gutfinger, S.K. Friedlander, Enhanced Deposition of Suspended Particles to Fibrous Surfaces from Turbulent Gas Streams, Aerosol Science and Technology, 2007. ISSN:0278-6826.
  13. K.T. Kim, J.Y. Choi, "Fine particle Removal Technology", Department of Mechanical Engineering - Environmental Particle Control Laboratory, KAIST.
  14. J.W. Park, A Study on Numerical Modeling of Aerosol Behavior Dynamics for Nuclear Reactor Safety Studies, KiSTi, 1993. KOSEF903-1210-001-2.
  15. S.H. Park, D.H. Kim, K.R. Kim, A Restructuring of RN1 Package for MIDAS Computer Code, 2003. KNS 2003-Autumn.
  16. S.J. Han, T.W. Kim, K.I. Ahn, An approach to estimation of radiological source term for a severe nuclear accident using MELCOR code, KAERI, J. Soc. Safety 27 (6) (2012) 192-204.
  17. S.H. Park, K.I. Ahn, D.H. Kim, H.D. Kim, A restructuring of the MELCOR code to establish the MIDAS computer code, J. Korea Info. Scie. Soc. 10 (12) (2012) 151-158.
  18. KAERI, MELCOR Code Modeling for APR1400, 2001. KAERI/TR-1847/2001.
  19. K.K. Murata, et al., Code Manual for CONTAIN 2.0:A Computer Code for Nuclear Reactor Containment Analysis, Sandia National Laboratory, 1997. NUREG/CR-6533, SAND97-1735.
  20. Larry Humphries, MELCOR RN Package Aerosol and Vapor Physics, Sandia National Laboratories, 2015.
  21. F. Gelbard, J.H. Seinfeld, Simulation of multicomponent aerosol dynamic, J. Colloid Interface Sci. 78 (2) (1980).
  22. C. Yoon, G.S. Ha, H.S. Lim, Development and validation of the aerosol inertial deposition model for analyzing fission product behavior in NPPs, J. Mech. Sci. Technol. (2013) 4143-4148. ISSN : 1738-494X.
  23. C. Yoon, H.S. Lim, Development of analytic computer software for the aerosol fission products behavior in VHTR's, in: 2013 KSME Meeting of Micro/Nano Engineering Division, 2013.
  24. Korea Atomic Industrial Forum, The 20th Nuclear Industry Survey Report, 2014.
  25. J. Onodera, C. Nakakmura, H. Yabuta, Y. Yokosuka, T. Nisizono, Y. Ikezawa, "Radiation Control Experience during JPDR Decommissioning", Japan Atomic Energy Research Institute.
  26. J. Dadoumont, V. Massaut, M. Klein, Y. Demeulemeester, "Decommissioning of a Small Reactor (BR3 Reactor, Belgium)", SCK-CEN, XA0201612.
  27. KAERI, A State-of-the Art on the Dismantling Techniques for the KRR-1 & 2 Decommissioning, 2001. KAERI/AR-609/2001.
  28. Lawrence E. Boing, "Dismantlement Technologies", Argonne National Laboratory Decommissioning Program.
  29. A draft document by a Task Group of Committee 2 of The International Commission on Radiological Protection, Human Alimentary Tract Model for Radiological Protection, 2004, 22/263/04.
  30. M.R. Bailey, E. Ansoborlo, R.A. Guilmette, F. Paquet, Updating the icrp human respiratory tract model, Radiat. Protect. Dosim. 127 (1-4) (2008) 31-34. https://doi.org/10.1093/rpd/ncm249
  31. IDEAS Report Summary, "Pilot Program Units of Contractors' Computer Codes with New Algorithms", FP5-EAECTP C, Ukraine.
  32. Final report of a joint IAEA-IDEAS project, Intercomparison Exercise on Internal Dose Assessment, 2007. IAEA-TECDOC-1568.
  33. A. Birchall, M.R. Bailey, A.C. James, Ludep : a Lung Dose Evaluation Program, OSTI, 1990. PNL-SA-18562, DE91 004071.
  34. NS-IAEA, "Verification of the LUDEP Software".
  35. C. James, Alan Birchall, James W. Marsh, Naomi S. Jarvis, IMBA Professional Plus (Vers. 4.0) User Manual Appendix C: Dose Quality Assurance, ACJ & Associates Inc, 2005.
  36. Anthony C. Jamaes, Development of computational code for internal dosimetry, in: U.S. Trans Uranium & Uranium Registries(USTUR), IRPA Regional Congress, Tokyo, Japan, 2010.
  37. U.S. Department of Energy, Gap Analysis for IMBA and DOE Safety Software Central Registry Recommendation, 2006. Final Report, DOE/EH-0711.
  38. U.S. Department of Energy, Guidance on Use of IMBA Software for DOE Safety Applications, 2006.
  39. T.Y. Lee, J.K. Kim, J.I. Lee, S.Y. Chang, The BiDAS program : bioassay data analysis software for evaluating radionuclide intake and dose, KAERI, J. Korean Radioactive Waste Soc. 2 (2) (2004) 113-124.
  40. KAERI, Development of Environmental Radiation Protection Technology - Technology Development for Evaluation of Operational Quantities in Radiation Protection, 2002. KAERI/RR-2358/2002.
  41. J.I. Lee, KAERI Internal Dose Assessment Quantity BiDAS Technology Status, KAERI, 2007.
  42. KAERI, The Assessment of Internal Doses for the Korean Nuclear Medicine Workers Based on the 131-I Bioassay Measurement, 2010. KAERI/CR-378/2010.
  43. J.I. Lee, T.Y. Lee, B.W. Kim, J.L. Kim, The Bidas-2007: Bioassay Data Analysis Software for Evaluating a Radionuclide Intake and Dose, Korea Atomic Energy Research Institute, 2009. Technical Note.
  44. KINS, A Study on Preparation of an Appraisal Method and Service Performance Criterion in Internal Exposure Focused on Domestic Nuclear Medicine, 2010. KINS/HR-1007, KRIA/RT-03-2010.
  45. EPA, Characterization and Generation of Metal Aerosols, Interagency Energy-Environment Research and Development, 1978. Program Report, EPA-600/7-78-013.

Cited by

  1. The “As Low As Reasonably Achievable” (ALARA) principle: a brief historical overview and a bibliometric analysis of the most cited publications vol.54, pp.2, 2018, https://doi.org/10.1051/radiopro/2019016
  2. Column Leaching Tests to Valorize a Solid Waste from the Decommissioning of Coal-Fired Power Plants vol.12, pp.9, 2018, https://doi.org/10.3390/en12091684
  3. Radiation Dosimetry of Inhaled Radioactive Aerosols: CFPD and MCNP Transport Simulations of Radionuclides in the Lung vol.9, pp.1, 2018, https://doi.org/10.1038/s41598-019-54040-1
  4. An External Dose Assessment of Worker during RadWaste Treatment Facility Decommissioning vol.45, pp.2, 2020, https://doi.org/10.14407/jrpr.2020.45.2.81