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Title:
METHOD FOR RECOVERING URANIUM FROM SPENT NUCLEAR FUEL BY HIGH ALKALI CARBONATE SOLUTION SYSTEM
Document Type and Number:
Japanese Patent JP2009265080
Kind Code:
A
Abstract:

To selectively separate and recover only uranium from spent nuclear fuel while having nuclear proliferation resistance and environmental affinity of minimizing the quantity of generated waste.

A recovery method includes the uranium dissolution-leaching stage of dissolving only uranium with hydrogen peroxide having the oxidizability between the oxidation-reduction equilibrium voltage of uranium oxide and the oxidation-reduction equilibrium voltage of plutonium oxide, neptunium oxide and americium oxide in a dissolver for a carbonate solution, the stage of precipitating and separating Cs and Tc with an organic precipitant, a uranium- precipitation and carbonate-recovery stage of precipitating uranium in a form of UO oxide, absorbing a generated carbon dioxide gas and allowing carbonate to recycle it by adjusting the carbonate solution containing the uranium to pH 2-4 with an acid in a uranium precipitation tank and the stage of recovering the acid and the alkali solution used in the uranium-precipitation and carbonate-recovery stage while removing metallic ions, impurities remaining in a solution from which the uranium and the carbonate are extracted.


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Inventors:
KIM KWANG WOOK
LEE EIL HEE
CHUNG DONG YOUNG
YANG HAN BUM
LIM JAE KWAN
CHO KEE SOO
SONG KEE CHAN
SONG KYU SEOK
JEE KWANG YONG
Application Number:
JP2008314631A
Publication Date:
November 12, 2009
Filing Date:
December 10, 2008
Export Citation:
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Assignee:
KOREA ATOMIC ENERGY RES
International Classes:
G21C19/46; B01D53/62; B01D61/44; C01G56/00; C22B3/04; C22B3/42; C22B3/44; C22B7/00; C22B60/02
Domestic Patent References:
JPH10332880A1998-12-18
JPS5669227A1981-06-10
Foreign References:
US4320923A1982-03-23
Attorney, Agent or Firm:
Masaki Hirota