Title:
METHOD AND DEVICE FOR RECOVERING SPENT NUCLEAR FUEL
Document Type and Number:
Japanese Patent JP3143853
Kind Code:
B2
Abstract:
PROBLEM TO BE SOLVED: To make the shape of a device compact and continuously recover useful metal elements from spent nuclear fuels without causing problems on critical safety management.
SOLUTION: In this method, a chloride-supported salt acting as a reacting medium is stored as a molten salt in a recovery tank 11 that has reaction chambers 15a to 15f, consisting of at least three chambers, along its inclining bottom 11a and is sealed and shaped into a plane which is thick enough to prevent spent nuclear fuel from reaching the critical state. Then, oxides of the spent nuclear fuel are supplied from the highest-level reaction chamber 15a, and uranium contained in the oxides is reacted with reactants in the highest-level reaction chambers 15a and 15b one after another to convert it into oxychlorines or uranium chlorides. The molten salt is electrolyzed in the medium-level chambers 15c and 15d to precipitate and recover uranium oxides, and chlorine gas and oxygen are blown into the lowest-level reaction chambers 15e and 15f to precipitate plutonium oxides contained in the molten salt. The precipitates are filtered away from the molten salt by discharging the liquid molten salt containing the precipitates of plutonium oxides from the lowest-level reaction chamber 15f.
Inventors:
Kazuaki Ohta
Takeshi Onoe
Hiroshi Takazawa
Sumio Yamagami
Takeshi Onoe
Hiroshi Takazawa
Sumio Yamagami
Application Number:
JP31269895A
Publication Date:
March 07, 2001
Filing Date:
November 30, 1995
Export Citation:
Assignee:
Mitsubishi Materials Corporation
International Classes:
G21C19/44; B01D19/00; (IPC1-7): G21C19/44; B01D19/00
Domestic Patent References:
| JP6265689A |
Attorney, Agent or Firm:
Masayoshi Suda
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