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Title:
METHOD FOR SEPARATING TECHNETIUM 99 IN HIGH LEVEL RADIOACTIVE WASTE SOLUTION
Document Type and Number:
Japanese Patent JP3034353
Kind Code:
B2
Abstract:

PURPOSE: To separate and recovery technetium 99 by contacting a waste solution with anion exchange resin and by adsorbing on it the nuclear species of the technetium 99 existing as the only anion chemical species in the waste solution.
CONSTITUTION: Actinide elements and rare earth elements in a radioactive waste solution of a high level are precipitated as oxalate by using oxalic acid. In the filtrate after the removal of these precipitates, alkaline metal elements, alkaline earth metal elements, platinum group elements, and other elements are dissolved in the forms of oxides and hydroxides, and the technetium 99 exists in the form of TcO4-. In a process for anion exchange, the filtrate is introduced into a column for anion exchange, and only the technetium 99 in the form of TcO4- is adsorbed and separated. As anion exchange resin, porous resin, of which both the exchange speed and the adsorptivity are large, is used. The adsorption of TcO4- is carried out in dilute nitric acid, and the elution is carried out in concentrated nitric acid.


Inventors:
Kamiya Motomiya
Reiko Fujita
Application Number:
JP22668891A
Publication Date:
April 17, 2000
Filing Date:
September 06, 1991
Export Citation:
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Assignee:
Toshiba Corporation
International Classes:
G21C19/46; G21F9/06; (IPC1-7): G21F9/06; G21C19/46
Domestic Patent References:
JP6423200A
JP1215727A
Attorney, Agent or Firm:
Saichi Suyama



 
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