Published October 7, 1994 | Version v1
Patent

Radioactive liquid wastes processing method and device therefor

Description

Liquid wastes containing sodium nitrate are charged into an adsorbent-filled column. Radioactive cations and radioactive anions are adsorbed and removed in the column. The liquid wastes flown out of the column are supplied to an intermediate undiluted solution chamber of an electrodialysis device. Cation exchange membranes isolate the intermediate undiluted solution chamber from a cathode chamber, and the intermediate diluted solution chamber from an anode chamber, respectively. In addition, the intermediate undiluted solution chamber and the intermediate diluted solution chamber are partitioned by an anion exchange membrane. The undiluted solution supplied to the intermediate undiluted solution chamber is separated to sodium ions and nitric acid ions, and the sodium ions are attracted to the cathode and transferred to the cathode chamber. The nitric acid ionsare attracted to the anode and transferred to the intermediate diluted solution chamber. With such procedures, only radioactive nuclide ions are separated from the low level radioactive liquid wastes, at the same time, anions contained in the liquid wastes are separated and recovered as acids and the sodium ions are removed and recovered as sodium hydroxide. (I.N.)

Availability note (English)

Available from JAPIO. Also available from EPO.

Additional details

Publishing Information

Imprint Pagination
6 p.
IPC:
Int. Cl. G21F9/06; C02F1/46; C02F1/469.
IPC
Int. Cl. G21F9/06; C02F1/46; C02F1/469.
Patent number
JP patent document 6-281790/A/

Optional Information

Secondary number(s)
JP patent application 5-66572.