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A STUDY ON ADSORPTION AND DESORPTION BEHAVIORS OF 14C FROM A MIXED BED RESIN

  • Park, Seung-Chul (Korea Hydro & Nuclear Power Co., LTD, Central Research Institute) ;
  • Cho, Hang-Rae (Korea Hydro & Nuclear Power Co., LTD, Central Research Institute) ;
  • Lee, Ji-Hoon (Korea Hydro & Nuclear Power Co., LTD, Central Research Institute) ;
  • Yang, Ho-Yeon (Korea Hydro & Nuclear Power Co., LTD, Central Research Institute) ;
  • Yang, O-Bong (Chonbuk National University, School of Semiconductor and Chemical Engineering & Solar Energy Research Center)
  • Received : 2014.07.18
  • Accepted : 2014.11.03
  • Published : 2014.12.25

Abstract

Spent resin waste containing a high concentration of $^{14}C$ radionuclide cannot be disposed of directly. A fundamental study on selective $^{14}C$ stripping, especially from the IRN-150 mixed bed resin, was carried out. In single ion-exchange equilibrium isotherm experiments, the ion adsorption capacity of the fresh resin for non-radioactive $HCO_3{^-}$ ion, as the chemical form of $^{14}C$, was evaluated as 11mg-C/g-resin. Adsorption affinity of anions to the resin was derived in order of $NO_3{^-}$ > $HCO_3{^-}{\geq}H_2PO_4{^-}$. Thus the competitive adsorption affinity of $NO_3{^-}$ ion in binary systems appeared far higher than that of $HCO_3{^-}$ or $H_2PO_4{^-}$, and the selective desorption of $HCO_3{^-}$ from the resin was very effective. On one hand, the affinity of $Co^{2+}$ and $Cs^+$ for the resin remained relatively higher than that of other cations in the same stripping solution. Desorption of $Cs^+$ was minimized when the summation of the metal ions in the spent resin and the other cations in solution was near saturation and the pH value was maintained above 4.5. Among the various solutions tested, from the view-point of the simple second waste process, $NH_4H_2PO_4$ solution was preferable for the stripping of $^{14}C$ from the spent resin.

Keywords

References

  1. International Atomic Energy Agency(IAEA), Application of Ion-exchange Processes for the Treatment of Radioactive Waste and Management of Spent Ion-exchange, Technical Report Series No. 408, IAEA, Vienna(2002).
  2. D. L. Moir, K. J. Ross, J. D. Chen and A. W. Tarr, E. L. Bialas, W. A. Boivin, D. C. Doern, D. L. Hoffman, and J. P. M. Ross, "Determination of $^{14}C$ in Spent Moderato rIon-Exchange Resin from Bruce Nuclear Generating Station A", J. Radioanal. & Nucl. Chem., 185(1), pp. 69-81(1994). https://doi.org/10.1007/BF02042953
  3. Wolsong Nuclear Power Plant, Final Safety Analysis Report, Wolsong NPP Unit 2,3,4, Vol. 7 (1995).
  4. W. Sohn, D.W. Kang and W.S. Kim, "An Estimate of Carbon-14 Inventory at Wolsong Nuclear Power Plant in the Republic of Korea", J. of Nuclear Science and Technology, 40, pp. 604-613(2003). https://doi.org/10.1080/18811248.2003.9715397
  5. US NRC, Code of Federal Regulations, Title 10, Chapter 1, Part 61, Licensing Requirements for Land Disposal of Radioactive Waste, Federal Register.47, 57446 (1982).
  6. KORAD Nuclear Waste Disposal Facility FSAR 8.3
  7. C. F. Wong and S. Vijayan, "Pre-Disposal Management of $^{14}C$-Bearing Organic-Resin Wastes", Waste Management'04, Proc. of the Symposium on Waste Management, Tucson, Feb. 29-Mar. Vol. 4, pp. 1-10, 2004, Arizona, USA.
  8. F. Chang, Carbon-14 Removal from Spent Ion-exchanged Resins Phase III-Pilot Evaluation, Report No. 91-19H, Ontario Hydro Research Division, Toronto (1991).
  9. Electric Power Research Institute(EPRI), The Treatment of Radioactive Ion-exchange Resins : Low-temperature Resin Oxidation Process, Report No. EPRI NP-7368s-M, EPRI, Palo Alto, CA (1991).
  10. S.W. Long, The Incineration of Low-level Radioactive Waste : A report for the Advisory Committee on Nuclear Waste, Report No. NUREG-1393, Nuclear Regulatory Commission, Washington, DC (1990).
  11. S.M. Crosley, et al., "Treatment of Waste by the Molten Salt Oxidation Process at the Oak Ridge National Laboratory", Nuclear Waste Management and Environmental Remediation (ICEM '93), Vol. 3, pp. 149-154, 1993, New York.
  12. C.M. Jantzen, D.K. Peeler and C.A. Cicero, Vitrifiction of Ion-exchange(IEX) Resins : Advantages and Technical Challenges, Report No. WSRC-MS-95-0518, Westinghouse Savannah River Co., Aiken, SC(1995).
  13. International Atomic Energy Agency(IAEA), Management of Waste Containing Tritium and Carbon-14, Technical Report Series No. 421, IAEA, Vienna(2004).
  14. M. S. Yim, F. Caron, "Life Cycle and Management of Carbon-14 from Nuclear Power Generation", Progress in Nuclear Energy, 48, pp 2-36 (2006). https://doi.org/10.1016/j.pnucene.2005.04.002
  15. Young-Il Jo, Su-Gu Lee, Yong-Ho Seon and Cheol-Hwi Park, Industrial Wastewater Disposal Engineering - Chapter 9 Ion-exchange, Donghwa Technology Publisher (2002)
  16. D. L. Parkhurst and C.A.J. Appelo, User's Guide to PHREEQC (Version 2), Water-Resources Investigations Report 99-4259.
  17. "Ion-exchange Resin : Amberlite IRN 150-Industrial Nuclear Grade Mixed Bed Resin", The Rohm and Hass, Amberlite/Amberjet Product Data Sheets (1993).
  18. I.H. Rhee, "Binary- and Ternary-Cation-exchanges : The Effect of Electrolyte Anions on Selectivity and Adsorption Capacity", J. of Korea Science Environ. Engng., 4(3), pp. 195-206 (1999).
  19. Gyeong-Deok Kim, Ho-Yeong Yang, et. al, Development of Disposal Technology of Spent Resin from Nuclear Power Plant (Removal of C-14), Report of Research and Development Project for Electric Power Industry, Korea Atomic Energy Research Institute - Nuclear Environment Technology Institute, TM.S03NJ05.M2005.04, pp. 187-188 (2005).