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

Korean Radioactive Waste Society (한국방사성폐기물학회)
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A Study on the Evaluation of Surface Dose Rate of New Disposal Containers Though the Activation Evaluation of Bio-Shield Concrete Waste From Kori Unit 1

  • Received : 2020.11.30
  • Accepted : 2021.01.28
  • Published : 2021.03.30
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Abstract

This study evaluates the radioactivity of concrete waste that occurs due to large amounts of decommissioned nuclear wastes and then determines the surface dose rate when the waste is packaged in a disposal container. The radiation assessment was conducted under the presumption that impurities included in the bio-shielded concrete contain the highest amount of radioactivity among all the concrete wastes. Neutron flux was applied using the simplified model approach in a sample containing the most Co and Eu impurities, and a maximum of 9.8×104 Bq·g-1 60Co and 2.63×105 Bq·g-1 152Eu was determined. Subsequently, the surface dose rate of the container was measured assuming that the bio-shield concrete waste would be packaged in a newly developed disposal container. Results showed that most of the concrete wastes with a depth of 20 cm or higher from the concrete surface was found to have less than 1.8 mSv·hr-1 in the surface dose of the new-type disposal container. Hence, when bio-shielded concrete wastes, having the highest radioactivity, is disposed in the new disposal container, it satisfies the limit of the surface dose rate (i.e., 2 mSv·hr-1) as per global standards.

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References

  1. Korea Hydro & Nuclear Power Co., Ltd. Development of NPP Decommissioning Source Terms Evaluation Technology, Korea Hydro & Nuclear Power Reports (2016).
  2. Electric Power Research Institute. Maine Yankee Decommissioning-Experience Report: Detailed Experiences 1997-2004, Electric Power Research Institute Report (2005).
  3. United States Nuclear Regulatory Commission. Inventory of Materials with Very Low Levels of Radioactivity Potentially Clearable from Various Types of Facilities, United States Nuclear Regulatory Commission Inventory Report (2001).
  4. K.Y. Lee, M.K. Oh, J.M. Kim, E.H. Lee, I.S. Kim, K.W. Kim, D.Y. Chung, and B.K. Seo, "Trends in Technology Development for the Treatment of Radioactive Concrete Waste", J. Nucl. Fuel Cycle Waste Technol., 16(1), 93-105 (2018). https://doi.org/10.7733/jnfcwt.2018.16.1.93
  5. Dominion Energy Kewaunee, Inc. Kewaunee Power Station Post-Shutdown Decommissioning Activities Report. Rev 0, Dominion Energy Kewaunee Report, 50-305 (2013).
  6. ZionSolutions, LLC. Zion Station Restoration Project: License Termination Plan Revision 2, ZionSolutions Report, 50-295 & 50-304 and 72-1037 (2018).
  7. H. Larsson, A. Anunti, and E. Mathias. Decommissioning Study of Oskarshamn NPP, Svensk Karnbranslehantering AB Tecnical Report, SKB-R-13-04 (2013).
  8. B.Y. Min, J.W. Park, W.K. Choi, and K.W. Lee, "Separation of Radionuclide from Dismantled Concrete Waste", J. Nucl. Fuel Cycle Waste Technol., 7(2), 79-86 (2009).
  9. G.Y. Cha, S.Y. Kim, J.M. Lee, and Y.S. Kim, "The Effects of Impurity Composition and Concen-Tration in Reactor Structure Material on Neutron Activation Inventory in Pressurized Water Reactor", J. Nucl. Fuel Cycle Waste Technol., 14(2), 91-100 (2016). https://doi.org/10.7733/JNFCWT.2016.14.2.91
  10. J.S. Lee, J.Y. Min, K.N. Jeon, and B.N. Lee, "Activation Properties to Aggregates Type for Low-Activation Concrete", AURIC 26(2) (2014).
  11. J.C. Evans, E.L. Lepel, R.W. Sanders, C.L. Wilkerson, W. Silker, , C.W. Thomas, K.H. Abel, and D.R. Robertson. Long Lived Activation Products in Reactor Materials, Pacific Northwest Laboratory Technical Report, NUREG/CR-3474 (1984).
  12. T. Zager, M. Bozic, and M. Ravnik, "Long-Lived Activation Products in TRIGA Mark II Research Reactor Concrete Shield: Calculation and Experiment", J. Nucl. Mater., 335(3), 379-386 (2004). https://doi.org/10.1016/j.jnucmat.2004.07.047
  13. K. Masumoto, A. Toyoda, K. Eda, Y. Izumi, and T. Shibata, "Evaluation of Radioactivity Induced in the Accelerator Building and its Application to Decontamination work", J. Radioanal. Nucl. Chem, 255, 465-469 (2003). https://doi.org/10.1023/A:1022511811356
  14. G. Hampel, F. Scheller, W. Bernnart, G. Pfister, U. Klaus, and E. Gerhards, "Calculation of the Activity Inventory for the TRIGA Reactor at the Medical University of Hannover (HMM) in Preparation for Dismantling the Facility", WM Symposia, Inc., Vol.35, February 24-28, 2002, Tucson, Arizona.
  15. Nuclear Study and Security Commission. Development of Radiation Safety Control Technology for a Giant Radiation Factory, Nuclear Safety and Security Commission Report, MONO120141529 (2013).
  16. Korea Radioactive Waste Agency. Development of Waste Package, Transportation and Disposal Containers for Decommissioning Wastes of Nuclear Power Plant, Korea Radioactive Waste Agency Technical Report (2019).