Magyar Asvanyolaj Es Foldgaz Kiserleti Intezet

Gyula Mozes

Peter Tilky

Tamas Drozda

Eva Hanel

Mihaly Kristof

Tibor Balint

A complex separation process and apparatus for decreasing non-radioactive salt content of waste solutions of nuclear power stations. The process significantly decreases in non-radioactive salt-content of waste solutions arising from nuclear power stations. Process is essentially based upon a suitable combination of up-to-date separating operations, such as precipitation, filtration, ultra-filtration, reverse osmosis, ion-exchange, evaporation and crystallization. Practically total amount of components carrying radioactivity (except tritium) can be effectively separated from the non-radioactive salts. Part of inactive salts (alkali nitrates) can be handled as industrial waste and the other part (boric acid) can be recycled. In the process precipitation, ion-exchange, reverse osmosis and crystallization are operations completing or replacing each other. Reverse osmosis is used not only for separating water and soluble, but for the separation of solved components.

Growing community of inventors

Veszprem, Hungary

Gyula Mozes