Radioactive waste organic solvent tributyl phosphate pyrolyzing furnace ash treatment method

A technology of tributyl phosphate and organic solvents, which is applied in the field of radioactive nuclear waste treatment, can solve the problems of increased volume of solidified body, minimization of unfavorable radioactive waste, leakage of long-lived radionuclides, etc., and achieves the effect of small size

Active Publication Date: 2019-05-31
SOUTHWEAT UNIV OF SCI & TECH
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  • Summary
  • Abstract
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  • Claims
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AI Technical Summary

Problems solved by technology

However, the cement solidification technology mainly has the following deficiencies: First, compared with the original volume of the pyrolysis furnace ash, the volume of the solidified body after cement solidification will increase significantly, which is not conducive to the minimization of radioactive waste; secondly, because the cement solidified body It has a porous structure, and the leaching rate of radionuclides in the cement solid

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0024] A method for treating radioactive waste organic solvent tributyl phosphate pyrolysis furnace ashes, the steps are: according to the composition and quality of 60% calcium pyrophosphate, 20% calcium hydroxide, 10% uranyl nitrate, and 10% calcium fluoride Percentage: Take the raw materials of each component and mix them to obtain a mixture; according to the mass percentage of 20% of the mixture, 40% of the grinding balls, and 40% of absolute ethanol, add the mixture, grinding balls, and absolute ethanol to the planetary ball mill Medium ball milling for 2 hours, the ball milling speed is 200 rpm, and then the ball milled material is dried at 40°C for 12 hours to obtain a dry powder; the dried powder is put into a steel mold, and the The machine adopts a pressure of 2 MPa and a holding time of 1 minute for compression molding, and then uses a pressure of 50 MPa and a holding time of 3 minutes for cold isostatic pressing on a cold isostatic press to obtain a formed body; Th...

Embodiment 2

[0026] A method for treating radioactive waste organic solvent tributyl phosphate pyrolysis furnace ashes, the steps are: according to the composition and quality of 65% calcium pyrophosphate, 15% calcium hydroxide, 10% uranyl nitrate, and 10% calcium fluoride Percentage: Take the raw materials of each component and mix them to obtain a mixture; according to the mass percentage of 15% of the mixture, 40% of the grinding balls, and 45% of absolute ethanol, add the mixture, grinding balls, and absolute ethanol to the planetary ball mill Medium ball milling for 3 hours, the ball milling speed is 250 rpm, and then the ball milled material is dried at 50°C for 16 hours to obtain a dry powder; the dried powder is put into a steel mold, and the The machine adopts a pressure of 9MPa and a holding time of 2 minutes for compression molding, and then uses a pressure of 110MPa and a holding time of 5 minutes for cold isostatic pressing on a cold isostatic press to obtain a molded body; Th...

Embodiment 3

[0028] A method for treating radioactive waste organic solvent tributyl phosphate pyrolysis furnace ashes, the steps are: according to the composition and quality of 70% calcium pyrophosphate, 15% calcium hydroxide, 10% uranyl nitrate, and 5% calcium fluoride Percentage: Take the raw materials of each component and mix them to obtain a mixture; according to the mass percentage of 20% of the mixture, 40% of the grinding balls, and 40% of absolute ethanol, add the mixture, grinding balls, and absolute ethanol to the planetary ball mill Medium ball milling for 5 hours, the ball milling speed is 300 rpm, and then the ball milled material is dried at 60°C for 20 hours to obtain a dry powder; the dried powder is put into a steel mold, and the The machine adopts a pressure of 16MPa and a holding time of 3 minutes for compression molding, and then uses a pressure of 170MPa and a holding time of 6 minutes for cold isostatic pressing on a cold isostatic press to obtain a molded body; Th...

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Abstract

The invention discloses a radioactive waste organic solvent tributyl phosphate pyrolyzing furnace ash treatment method which is characterized in that calcium pyrophosphate, calcium hydroxide, uranyl nitrate and calcium fluoride serve as raw materials and are ball-milled and dried to prepare powder, the powder is pressed on a tablet press and a cold isostatic press and pretreated to prepare a greenbody, and the green body is sintered by a flash burning technology to prepare a fluorapatite ceramic solidified body. The flash burning technology is applied to treatment of radioactive waste organicsolvent tributyl phosphate pyrolyzing furnace ash, and the prepared fluorapatite ceramic solidified body has the advantages of high mineralogical phase purity and compactness, low leaching rate and the like. Compared with existing other radioactive waste organic solvent tributyl phosphate pyrolyzing furnace ash treatment methods, the flash burning treatment method has the advantages of simple equipment, time-saving property, high efficiency, high technical controllability, economical efficiency, energy conservation, high practicability and the like.

Description

technical field [0001] The invention belongs to the treatment of radioactive nuclear waste, and relates to a treatment method for the pyrolysis furnace ash of radioactive waste organic solvent tributyl phosphate, which is suitable for the pyrolysis furnace ash of radioactive waste organic solvent tributyl phosphate in the Purex process. sintering treatment. Background technique [0002] It is estimated that by 2030, China's nuclear power plant spent fuel will accumulate about 23,500 tons, and the demand for off-reactor storage will reach 15,000 tons. The safe disposal of spent fuel in the future has become one of the key issues restricting the sustainable development of the nuclear industry. Spent fuel is the nuclear fuel in the nuclear fuel assembly that is unloaded from the reactor when the burnup depth reaches the design unloading burnup and is no longer used in the nuclear reactor. The typical radionuclide composition of spent fuel is as follows: about 94% uranium ( 23...

Claims

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Application Information

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IPC IPC(8): C04B35/447C04B35/622C04B35/64G21F9/30
Inventor 黄毅银航晏敏皓滕元成李玉香
Owner SOUTHWEAT UNIV OF SCI & TECH
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