TREATMENT OF RADIOACTIVE WASTE LIQUID CONTAINING SALTS AT HIGH CONCENTRATION
PURPOSE:To efficiently remove radioactive materials from radioactive waste liquid contg. salts at a high concn. by passing this waste liquid through capturing materials deposited and fixed with the ferrocynate compd. expressed by the specific formula and injecting a settling material thereto by inli...
Gespeichert in:
Hauptverfasser: | , |
---|---|
Format: | Patent |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext bestellen |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | PURPOSE:To efficiently remove radioactive materials from radioactive waste liquid contg. salts at a high concn. by passing this waste liquid through capturing materials deposited and fixed with the ferrocynate compd. expressed by the specific formula and injecting a settling material thereto by inline chemical injection. CONSTITUTION:The radioactive waste liquid contg. the salts at the high concn. is introduced from a storage tank via a feed pump 1 and a prefilter 2 into 1st-3rd adsorption columns 3-5. Active carbon is packed into the adsorption column 3 where radioactive cobalt is mainly removed from the liquid. The nuclide capturing material formed by depositing and fixing manganese dioxide on acrylic fibers is used in the adsorption column 4 were radioactive manganese, cerium, cobalt, etc., are removed from the liquid. The nuclide capturing material prepd. by depositing and fixing the ferrocyanate compd. expressed by the formula on acrylic fibers is used in the adsorption column 5. The liquid past the adsorption column 5 is mixed with the liquid chemicals from chemicals tanks 6, 7 and a high-polymer flocculating agent tank 8. The radioactive strontium is thus confined into the precipitate by the settling and flocculating and is captured by a filter 9. |
---|