Technical information

1. 　Many kinds of radioactive nuclides are contained in the waste solution from atomic power plants, such as 137Cs, 90Sr, 144Ce, 106Ru, and 95Zr, etc. Typical treatment techniques such as evaporation, ion-exchange, and chemical precipitation are conventionally used for separating those radioactive nuclides from waste solution.
   

1. As a high speed and safe treatment method of radioactive effluents, Co-precipitation Flotation was researched and developed by Dr. Y. Koyanaka, professor in Kyoto University Japan from 1966 to 1970. The specific features are as follows:
   

1. 1.Large treatment capacity of waste solution with a high yield and low cost
   

2. 2.Small amount of radioactive sludge from the treatment process
   

3. 3.High efficiency for removing radioactive nuclides under the wet process
   

1. We have a lot of knowhow to select and use the appropriate chemicals according to the kinds of radioactive nuclides contained in effluents. Our know-how can contribute to the treatment of a large quantity of radioactive effluents that will be produced from the process of atomic power reactors abolitions in this century.
   

Photograph of an actual flotation device

REFERENCES

Y. Koyanaka, Treatment of the Radioactive Sludge Produced by Precipitate Flotation Method, Annual Reports of the Research Reactor Institute, Kyoto University, Vol. 3,  pp.147-152,　(1970)

25. Y.Koyanaka, Treatment of Radioactive Waste Regenerant of Ion Exchange Resin by Preferential Flotation Method, Journal of Nuclear Science and Technology, Vol. 6,　No.10, 607-608, (1969)
    

Y. Koyanaka, Untersuchungen über die Trennung von Spaltprodukten nachder　Flotationsmethode - Die Abtrennung von 95Zr-95Nb , KFK-tr-242, Kernforschungsyentrum Karlsruhe  Literaturabteilung,　(1966)

Y. Koyanaka, Untersuchungen über die Trennung von Spaltprodukten nachder　Flotationsmethode - Die Abtrennung von 137Cs KFK-tr-228, Kernforschungsyentrum Karlsruhe  Literaturabteilung,　 (1966)