Published May 27, 1987 | Version v1
Patent

Recovering device for ruthenium from fuel reprocessing liquid wastes

Description

Purpose: To enable to easily recover ruthenium in liquid wastes and facilitate the liquid waste processing by easily oxidizing and gasifying ruthenium, cooling and condensating the same and causing to absorb by absorbent such as an alkali agent. Constitution: Nuclear fuel reprocessing solution supplied from a supply pipe to the inside of a reaction vessel is heated to about 130 - 180 deg C by a heat source. When the nitric acid concentration in the liquid wastes is increased in this state to higher than 5 N and, preferably, higher than 10 N, ozone is supplied from an oxidizer introduction pipe as oxidizer supply means. Ruthenium in the liquid wastes is oxidized with ozone under the presence of nitric acid into a gaseous form, flown together with ozone and exhaust gas such as carrier gas to an exit pipe and cooled. Then, the cooled gas is introduced to the inside of an absorbing device where gaseous ruthenium oxide is recovered together by an absorbent liquid such as alkali sprayed and circulated in the device. The gas after the recovery is discharged by way of the discharge pump. In this way, ruthenium can be recovered from the liquid wastes. (Yoshino, Y.)

Availability note (English)

Available from JAPIO. Also available from INPADOC.

Additional details

Publishing Information

Imprint Pagination
3 p.
IPC:
Int. Cl. G21F9/06; G21F9/16.
IPC
Int. Cl. G21F9/06; G21F9/16.
Patent number
JP patent document 62-115399/A/

Optional Information

Secondary number(s)
JP patent application 60-253649.