Review

  • Journal of Nuclear Fuel Cycle and Waste Technology
  • Volume 4(4); 2006
  • Article

Journal of Nuclear Fuel Cycle and Waste Technology 2006;4(4):373-384. Published online: Dec, 30, 2006

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Gasification Characteristics to 14CO2 of 14C Radionuclide Desorbed from Spent Resin by Phosphate Solutions

  • Ho-Yeon Yang ; Jang-Sik Won ; Young-Ku Choi ; Geun-IL Park ; In-Tae Kim ; Kwang-Wook Kim ; Kee Chan Song ; Hwan Seo Park
Abstract

Spent ion-exchanged resin generated from various purification systems in CANDU reactor was contaminated with high activity of 14C radionuclide. This paper describes the results of fundamental study to develop the applicable technology for the treatment of this spent resin. Based on the adsorption capacity of inactive HCO3- ion and other anions on IRN-150 mixed resin, the removal characteristics of HCO3- ion adsorbed on to IRN-150 by various stripping solutions were evaluated. Maximum adsorption amount of the HCO3- ion onto IRN-150 raw resin was about 11 mg-C/g-resin which agrees with the theoretical adsorption amount of this resin. Adsorption affinity of various anions such as Cs, Co, Na, NH4 was analyzed in single and multi-component systems. From the results of removal characteristics of the HCO3- ion adsorbed on IRN-150 by various stripping solutions, NH4H2PO4 stripping solution is more effective than NaNO3, Na3PO4 solutions for the complete removal of 14C radionuclide from the IRN-150 spent resin.

Keywords

CANDU reactor,Spent resin,14C radionuclide,Anion,Adsortpion,Stripping solution