Journal of Radioanalytical and Nuclear Chemistry

, Volume 285, Issue 2, pp 177–186 | Cite as

Gasification characteristics to 14CO2 of 14C radionuclide desorbed from spent resin by phosphate solutions

  • Ho-Yeon Yang
  • Ji-Hoon Lee
  • Jung-Jin Lee


The removal characteristics of H14CO3 ions from IRN-150 mixed resin contaminated with 14C radionuclide and the gasification effects of 14C radionuclide on 14CO2 are investigated in this study. The stripping solutions used for the removal of 14C from spent resin are NaNO3, Na3PO4, NH4H2PO4, and H3PO4. The influence of the stripping solution concentration on the desorption characteristics of an inactive HCO3 ion into a stripping solution from IRN-150 mixed resin and the gasification of this ion to CO2 is analyzed. The gasification behavior to CO2 using NaOH, HNO3, and HCl was also compared to that of phosphate solution. Spent resin stored in Wolsong nuclear power plant is used to evaluate the gasification characteristics of 14C radionuclide to 14CO2. Gamma radionuclides such as 137Cs and 60Co in residual striping solutions after desorption experiments are analyzed.


14C radionuclide Spent resin Stripping solution 14CO2 Gasification 



This study was performed as a part of the research and development of products for the electric power industry sponsored by the Ministry of Industry and Resources (now the Ministry of Knowledge Economics).


  1. 1.
    Sohn W, Kang DW, Kim WS (2003) An Estimate of Carbon-14 Inventory at Wolsong Nuclear Power Plant in the Republic of Korea. J Nucl Sci Technol 40:604–613CrossRefGoogle Scholar
  2. 2.
    Yim MS, Caron F (2006) Life cycle and management of Carbon-14 from nuclear power generation. Prog Nucl Energy 48:2–36CrossRefGoogle Scholar
  3. 3.
    Wolsong Nuclear Power Plant, Final Safety Analysis Report, Wolsong NPP Units 2, 3 and 4, Vol. 7 (1995)Google Scholar
  4. 4.
    Boss CR, Allsop PJ (1995) Radioactive effluents from CANDU 6 Reactor during normal operation, Atomic Energy of Canada Limited, Chalk River, Ont., AECL-11506Google Scholar
  5. 5.
    International Atomic Energy Agency (IAEA) (2002) Application of ion exchange processes for the treatment of radioactive waste and management of spent ion exchange, Technical Report Series No. 408, IAEA, ViennaGoogle Scholar
  6. 6.
    Yang H-Y, Kim G-D, Lee S-J, Won J-S (2005) Development of disposal technology of spent resin from nuclear power plant (Removal of C-14), Nuclear Environment Technology Institute, KHNP, TM.S03NJ05.M2005.04, pp 187–188Google Scholar
  7. 7.
    US NRC (1982) Code of Federal Regulations, Title 10, Chapter 1, Part 61, Licensing requirements for land disposal of radioactive waste, Federal Register. 47, 57446Google Scholar
  8. 8.
    Wong CF, Vijayan S (2004) Pre-disposal management of 14C-bearing organic-resin wastes. In: Waste Management ‘04, Proc. of the Symposium on Waste Management, Tucson, Feb. 29–Mar. Vol 4, pp 1–10, Arizona, USAGoogle Scholar
  9. 9.
    International Atomic Energy Agency (IAEA) (2004) Management of waste containing tritium and Carbon-14, Technical Report Series No. 421, IAEA, ViennaGoogle Scholar
  10. 10.
    Ion Exchange Resin: Amberlite IRN 150-Industrial Nuclear Grade Mixed Bed Resin, The Rohm and Hass, Amberlite/Amberjet Product Data Sheets (1993)Google Scholar
  11. 11.
    Matsuzuru H, Kobayashi Y, Dojiri S, Akatsu J, Morijama N (1983) A comparison of the acid digestion of spent ion exchange resins using H2SO4–HNO3 and H2SO4–H2O2. Nucl Chem Waste Manage 4(4):307–312CrossRefGoogle Scholar
  12. 12.
    Parkhurst DL, Appelo CAJ, User’s Guide to PHREEQC (Version 2), Water-Resources Investigations Report 99-4259Google Scholar
  13. 13.
    Yang HY, Won JS, Choi YK, Park GI, Kim IT, Kim KW, Song KC, Park HS (2006) Ion Adsorption characteristics of ion by IRN-150 mixed resin and removal behavior of 14C radionuclide from spent resin by stripping solution. J Korean Radioact Waste Soc 4(4):373–384Google Scholar
  14. 14.
    Eun HC, Yang HC, Cho YZ, Lee HS (2009) Study on a stable destructive method of radioactive waste ion exchange resins. J Radioanal Nucl Chem 281:585–590CrossRefGoogle Scholar
  15. 15.
    Gupta KK, Singh SK, Inamdar GA, Madhusudan A, Tripathi SC (2009) Studies on decontamination of spent ion exchange resin used for plutonium purification in PUREX stream. J Radioanal Nucl Chem 281:609–614CrossRefGoogle Scholar
  16. 16.
    Park SD, Kim JS, Han SH, Jee KY (2008) Distribution characteristics of 14C and 3H in spent resins from the Canada deuterium uranium-pressurized heavy water reactors (CANDU-PHWRs) of Korea. J Radioanal Nucl Chem 277(3):503–511CrossRefGoogle Scholar
  17. 17.
    Magnusson A, Stenstrom K, Aronsson PO (2008) 14C in spent ion-exchange resins and process water from nuclear reactors: a method for quantitative determination of organic and inorganic fractions. J Radioanal Nucl Chem 275(2):261–273CrossRefGoogle Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2010

Authors and Affiliations

  1. 1.Nuclear Engineering & Technology Institute, KHNPYuseong-gu, DaejeonKorea

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