Published October 26, 1992 | Version v1
Patent

Processing method for radioactive liquid waste

Description

Liquid wastes generated upon electropolishing of metals such as carbon steel and stainless steel contaminated by uranium (U) are processed to remove most of U and heavy metals. An aqueous solution of magnesium salt is dissolved in the radioactive liquid wastes containing a slight amount of heavy metals (Fe, Ni and Cr) and U, and subsequently, water glass is added. Further, an alkali solution is added to control pH to 8 to 9, and a water glass precipitate is formed to remove heavy metals and U. With such procedures, since heavy metals such as Fe, Ni and Cr and U are agglomerated in the water glass precipitates, radioactive wastes can be processed by removing the water glass precipitates. Further, according to this method, U in the liquid wastes can be completely removed to less than a detection limit, as well as heavy metals can be reduced to less than a regulated value. (T.M.)

Availability note (English)

Available from JAPIO. Also available from INPADOC.

Additional details

Publishing Information

Imprint Pagination
5 p.
IPC:
Int. Cl. G21F9/16.
IPC
Int. Cl. G21F9/16.
Patent number
JP patent document 4-301799/A/

Optional Information

Secondary number(s)
JP patent application 3-91698.