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Removal behavior of Cs from molten salt by using zeolitic materials

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Abstract

Radioactive molten salt generated from a pyrochemical process to separate reusable U and TRU elements is one of problematic wastes to manage for a final disposal. For the minimization of final waste, it is desirable to selectively remove radionuclides from the waste salts. In this paper, structural change of some zeolites in a series of molten salt systems and its removal behavior of CsCl was investigated. Zeolite-4A(LTA) was transformed into LiAlSiO4 and Li-sodalite with the mol-fraction of LiCl in LiCl–KCl system at 650 °C while it was not changed in NaCl–KCl at 750 °C, regardless of mol-fraction of metal chloride. Other commercial zeolite with specific structure (FAU) had the same trends on the structural stability in molten salt system. From the Cs removal experiments, the decomposed zeolitic materials in molten salt lost their removal ability of Cs. In conclusion, a new selective material or method should be investigated or developed for obtaining the validity on the separation of group I and II radionuclides from a molten waste salt because the zeolite 4A is unstable in the LiCl system and it also showed a low capacity in the LiCl–KCl phase. This paper gives basic information on the removal of radionuclides from molten systems by using zeolitic materials.

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Authors and Affiliations

  1. Advanced Fuel Cycle Development, Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong-gu, Daejeon, 305-353, South Korea

    Hwan-Seo Park, In-Tae Kim, Yong-Jun Cho, Mi-Sook Son & Hee-Chul Eun

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  1. Hwan-Seo Park
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  2. In-Tae Kim
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  3. Yong-Jun Cho
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  4. Mi-Sook Son
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  5. Hee-Chul Eun
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Correspondence to Hwan-Seo Park.

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Park, HS., Kim, IT., Cho, YJ. et al. Removal behavior of Cs from molten salt by using zeolitic materials. J Radioanal Nucl Chem 283, 267–272 (2010). https://doi.org/10.1007/s10967-009-0351-9

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  • DOI: https://doi.org/10.1007/s10967-009-0351-9

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