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Curing method of high-salt radioactive waste liquid

A technology of radioactive waste liquid and solidification method, which is applied in radioactive purification, nuclear engineering, etc., can solve the problems of low water ash, achieve the effects of not reducing performance, increasing wrapping rate, and improving water-cement ratio

Pending Publication Date: 2019-11-22
SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] In order to solve the problem of low water-cement ratio of phosphate cement solidified body in the prior art, the present invention provides a solidification method of high-salt radioactive waste liquid

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0019] Weigh 32g of potassium dihydrogen phosphate, 160g of dead-burned magnesia, 32g of silica fume, and 16g of borax respectively, put each raw material into a stirring container and mix evenly, add 72ml of high-salt radioactive waste liquid, and stir for 2 minutes to obtain a slurry Inject it into a steel mold, keep it in the air at room temperature for 1 hour, and the green body is formed. Put the green body into a high-temperature furnace, raise the temperature at 20°C / min to 800°C and keep it warm for 4 hours, and then cool it down to room temperature naturally with the furnace to obtain mineral phases containing k-struvite, phosphatite, stevensite, etc. High-salt radioactive waste liquid phosphate ceramic solidified body.

Embodiment 2

[0021] Weigh 48g of potassium dihydrogen phosphate, 160g of dead-burned magnesia, 32g of silica fume, and 16g of borax respectively, put each raw material into a stirring container and mix evenly, add 76.8ml of high-salt radioactive waste liquid, and stir for 2 minutes to obtain the The slurry is injected into the steel mold, kept in the air at room temperature for 1 hour, and the green body is formed. Put the green body into a high-temperature furnace, raise the temperature at 20°C / min to 800°C and keep it warm for 4 hours, and then cool it down to room temperature naturally with the furnace to obtain mineral phases containing k-struvite, phosphatite, stevensite, etc. High-salt radioactive waste liquid phosphate ceramic solidified body.

Embodiment 3

[0023] Weigh 32g of potassium dihydrogen phosphate, 160g of dead-burned magnesia, 32g of silica fume, and 16g of borax respectively, put each raw material into a stirring container and mix evenly, add 84ml of high-salt radioactive waste liquid, and stir for 2 minutes to obtain a slurry Inject it into a steel mold, keep it in the air at room temperature for 1 hour, and the green body is formed. Put the green body into a high-temperature furnace, raise the temperature at 20°C / min to 800°C and keep it warm for 4 hours, and then cool it down to room temperature naturally with the furnace to obtain mineral phases containing k-struvite, phosphatite, stevensite, etc. High-salt radioactive waste liquid phosphate ceramic solidified body.

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Abstract

The invention relates to a curing method of high-salt radioactive waste liquid. The curing method comprises the following steps: providing phosphate ceramic raw materials of potassium dihydrogen phosphate, dead burnt magnesia, silica fume and a retarder in a mass ratio of (0.2-0.3):1:0.2:0.1; providing high-salt radioactive waste liquid containing radionuclide and fluorine element and having saltcontent of more than 200 g / L; at room temperature, adding the high-salt radioactive waste liquid into a phosphate ceramic raw material, and stirring the mixture to obtain slurry, and injecting the slurry into a mold, and molding the slurry to obtain a green body, wherein the mass ratio of the high-salt radioactive waste liquid to the phosphate ceramic raw material is 0.3-0.35:1; and sintering thegreen body at 800-900 DEG C to enable all components in the phosphate ceramic raw material to be reacted to generate a mineral phase to wrap radionuclide and fluorine in the high-salt radioactive waste liquid, so as to obtain a phosphate ceramic solidified body. The water-cement ratio is increased by increasing the wrapping rate of the high-salt radioactive waste liquid, the volume of a solidifiedbody is reduced, and the principle of waste minimization is met.

Description

technical field [0001] The invention relates to ceramic solidification, more particularly to a solidification method of high-salt radioactive waste liquid. Background technique [0002] The radioactive waste liquid produced by the thorium-uranium fuel cycle experiment is a waste source item with a complex system of "radiation-chemical corrosion-fluorine salt". After pretreatment by the wastewater treatment system, high-salt radioactive waste liquid rich in fluoride will be produced. In order to reduce the possibility of radioactive nuclides and fluorine elements migrating to the environment during the disposal process, and to protect the ecological environment and public health, the regulations on radioactive waste management require that these high-salt radioactive waste liquids be treated to convert them into stable waste forms. [0003] Phosphate cementitious material is a new type of material that forms chemical bonds based on acid-base neutralization reaction to generat...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/16
CPCG21F9/165
Inventor 钱正华刘学阳乔延波王帅秦强施柳青余博文周顺
Owner SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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