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Recycling of isotopically modified molybdenum from irradiated CerMet nuclear fuel: part 2—caesium separation from concentrated molybdate solution

  • Kamil Vavřinec MarešEmail author
  • Ferdinand Šebesta
  • Jan John
Article
  • 4 Downloads

Abstract

As described in a previous paper (Mareš and John in J Radioanal Nucl Chem, 2019.  https://doi.org/10.1007/s10967-019-06456-2), isotopically manipulated molybdenum used as an inert matrix in advanced types of nuclear fuels should be recycled. This study aimed to demonstrate the possibility of removing caesium from concentrated molybdenum solutions resulting from the proposed molybdenum reprocessing procedure. The commercially available DOWEX 50W, Amberjet 1000H, Crystalline Ionsiv IE910 and IE 911 exchangers as well as four in-house prepared hexacyanoferrates (Nickel, Potassium-nickel, Potassium-cooper and Potassium-cobalt) were tested in batch and column experiments. The results revealed that KNiFC-PAN resin is the most promising ion exchanger for caesium separation from a slightly alkaline (pH 9.1) ammonium molybdate solution.

Keywords

CerMet fuel Molybdenum recycling Caesium Ion-exchange Hexacyanoferrates Polyacrylonitrile PAN 

Notes

Acknowledgements

This study was supported by the ASGARD Project supported by EU within the 7th Framework Programme (EC-GA No. 295825), the Grant Agency of the Czech Technical University in Prague (Grants No. SGS12/199/OHK4/3T/14 and SGS15/216/OHK4/3T/14), and by the Centre for advanced applied science, Project Number CZ.02.1.01/0.0/0.0/16_019/0000778, supported by the Ministry of Education, Youth and Sports of the Czech Republic.

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Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2019

Authors and Affiliations

  1. 1.Department of Nuclear ChemistryCzech Technical University in PraguePrague 1Czech Republic

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