Treatment Method for Volume Reduction of Spent Uranium Catalyst
First Claim
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1. A treatment method of a spent uranium catalyst comprising the following steps:
- selectively dissolving the support component by immersing the spent uranium catalyst in an alkali solution (step
1);
separating the dissolution solution and the undissolved solid materials in the step 1 by solid-liquid separation (step
2);
selectively precipitating the silicon ions included in the dissolution solution as silicon dioxide (step
3);
separating the silicon dioxide generated in step 3 by solid-liquid separation and its purification (step
4);
precipitating uranium ions as uranium phosphate by adding phosphate to the residual solution separated in the step 4 (step
5);
separating the uranium phosphate generated in step 5 by solid-liquid separation (step
6);
mixing the undissolved solid materials separated in step 2 with the precipitate of uranium phosphate separated in step 6 and then adding a glassification agent thereto, followed by heat-treatment to fix the mixture in the form of a glass-ceramic composite medium (step
7).
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Abstract
The present invention relates to a volume reduction treatment method of a spent uranium catalyst. According to the volume reduction treatment method of a spent uranium catalyst of the present invention, the disposal cost of the spent uranium catalyst can be reduced and the utilization of the repository can be improved since the method can significantly reduce the volume of the final disposal waste of the spent uranium catalyst.
1 Citation
21 Claims
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1. A treatment method of a spent uranium catalyst comprising the following steps:
-
selectively dissolving the support component by immersing the spent uranium catalyst in an alkali solution (step
1);separating the dissolution solution and the undissolved solid materials in the step 1 by solid-liquid separation (step
2);selectively precipitating the silicon ions included in the dissolution solution as silicon dioxide (step
3);separating the silicon dioxide generated in step 3 by solid-liquid separation and its purification (step
4);precipitating uranium ions as uranium phosphate by adding phosphate to the residual solution separated in the step 4 (step
5);separating the uranium phosphate generated in step 5 by solid-liquid separation (step
6);mixing the undissolved solid materials separated in step 2 with the precipitate of uranium phosphate separated in step 6 and then adding a glassification agent thereto, followed by heat-treatment to fix the mixture in the form of a glass-ceramic composite medium (step
7). - View Dependent Claims (2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21)
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Specification