Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
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Safety Analysis of Concrete Treatment Workers in Decommissioning of Nuclear Power Plant

  • Received : 2022.07.26
  • Accepted : 2022.08.26
  • Published : 2022.09.30
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Abstract

Nuclear power plant decommissioning generates significant concrete waste, which is slightly contaminated, and expected to be classified as clearance concrete waste. Clearance concrete waste is generally crushed into rubble at the site or a satellite treatment facility for practical disposal purposes. During the process, workers are exposed to radiation from the nuclides in concrete waste. The treatment processes consist of concrete cutting/crushing, transportation, and loading/unloading. Workers' radiation exposure during the process was systematically studied. A shielding package comprising a cylindrical and hexahedron structure was considered to reduce workers' radiation exposure, and improved the treatment process's efficiency. The shielding package's effect on workers' radiation exposure during the cutting and crushing process was also studied. The calculated annual radiation exposure of concrete treatment workers was below 1 mSv, which is the annual radiation exposure limit for members of the public. It was also found that workers involved in cutting and crushing were exposed the most.

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References

  1. K. Kim, E. Cumming, and R. McGrat. Concrete Characterization and Dose Modeling During Plant Decommissioning, Electric Power Research Institute Technical Report, 1015502 (2008).
  2. M. Snyder and R. Cardarelli. Characterization and Remediation of Contaminated Concrete, Electric Power Research Institute Technical Report, 3002005412 (2015).
  3. J. Wall, T. Esselman, P. Bruck, and B. Forget. Expected Condition of Reactor Cavity Concrete After 80 Years of Radiation Exposure, Electric Power Research Institute Technical Report, 3002002676 (2014).
  4. E. Wong and P. Bruck. Irradiation Damage of the Concrete Biological Shield: Basis for Evaluation of Concrete Biological Shield Wall for Aging Management, Electric Power Research Institute Technical Report, 3002011710 (2018).
  5. R. Reid, J. Roll, and J. Collin. Best Practices for the Decontamination, Reuse, and Recycle of Contaminated Metal and Concrete, Electric Power Research Institute Technical Report, 3002020927 (2021).
  6. Nuclear Safety and Security Commission, Regulation on the Criteria for the Classification and Clearance of Radioactive Wastes, NSSC Notice No. 2020-6 (2020).
  7. S.B. Hong, B.K. Seo, E.J. Lee, and I.H. Hamh. Radiological Dose Assessment for Clearance of Radioactive Concrete Waste, TSS Report (2019).
  8. R. Anigstein, H.J. Chmelynski, D.A. Loomis, S.F. Marschke, J.J. Mauro, R.H. Olsher, W.C. Thurber, and R.A. Meek. Radiological Assessments for Clearance of Materials From Nuclear Facilities, U.S. Nuclear Regulatory Commission Report, NUREG-1640 (2003).
  9. International Atomic Energy Agency, Application of Exemption Principles to the Recycle and Reuse of Materials From Nuclear Facilities, IAEA Safety Series, No. 111-P-1.1 (1993).
  10. International Atomic Energy Agency, International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources, IAEA Safety Series, No.115 (1996).