Complex preparation-process for decreasing the non-radioactive salt content of waste solutions of nuclear power stations
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United States of America Patent
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Jan 8, 1991
Grant Date -
N/A
app pub date -
Mar 25, 1986
filing date -
Sep 12, 1984
priority date (Note) -
Expired
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Abstract
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.
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