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Method for solidifying radioactive solid waste cement

A technology of radioactive waste and cement solidification, applied in radioactive purification, nuclear engineering and other directions, can solve the problems of unmeasured leaching performance and no improvement, and achieve the improvement of anti-leaching performance, improving anti-leaching performance and strength, and improving treatment effect. Effect

Pending Publication Date: 2022-06-24
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Moreover, although the unfavorable high leachability of this type of method has also been mentioned in this document, it has not been improved, and its examples have not measured the leachability

Method used

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  • Method for solidifying radioactive solid waste cement

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0044] Mix 1000g of ordinary Portland cement, 50g of silica fume and 15g of sulfonated phenolic resin uniformly, pour 350ml of water into the stirring pot, and then mix the uniformly mixed material and 200ml of radioactive catalyst (activated carbon carrier, active component Ru, active The mass fraction of the components is 3%, and the particle size is 1 mm) into a stirring pot and stirred for about 4 minutes. The volume of the cement slurry was measured, and the volume inclusion rate of the available catalyst was 27v%.

[0045] Pour the mixed cement slurry into the mold and put it into the curing box. The curing temperature is 25±5°C, the humidity is greater than 90%, and the cured body is made after curing for 28 days.

Embodiment 2

[0047] Mix 1000g of ordinary Portland cement, 50g of silica fume and 15g of sulfonated phenolic resin evenly, pour 300ml of water into the stirring pot, and then mix the well-mixed dry powder and 200ml of radioactive catalyst (activated carbon carrier, active component Pt, The mass fraction of active components is 5%, and the particle size is 1 mm) into a stirring pot and stirred for about 4 minutes. The volume of the cement slurry was measured, and the volume inclusion rate of the available catalyst was 27v%. Subsequent operations are the same as in Example 1.

Embodiment 3

[0049] Mix 1000g of ordinary Portland cement, 100g of silica fume and 20g of sulfonated phenolic resin evenly, pour 350ml of water into the stirring pot, and then mix the well-mixed dry powder and 200ml of radioactive catalyst (activated carbon carrier, active component Ru / Pt, active component mass fraction of 5%, particle size of 10 mm) was poured into a stirring pot and stirred for about 4 minutes. The volume of the cement slurry was measured, and the volume inclusion rate of the available catalyst was 25v%. Subsequent operations are the same as in Example 1.

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Abstract

The invention provides a cement solidification treatment method for a radioactive waste catalyst, which comprises the following steps: mixing and solidifying the radioactive waste catalyst and a cement composition to obtain a cement solidified body, and the volume inclusion rate of the radioactive waste catalyst in the cement solidified body is 20-40v%; the cement composition comprises ordinary Portland cement, silica fume and sulfonated phenolic resin, and the mass part ratio of the ordinary Portland cement to the silica fume to the sulfonated phenolic resin is 1000: (30-300): (5-30). The 42-day nuclide leaching rate of the cement solidified body obtained by the method disclosed by the invention is 2 orders of magnitude lower than that of the national standard.

Description

technical field [0001] The invention belongs to the technical field of radioactive solid waste treatment, and particularly relates to a cement solidification treatment method for radioactive waste catalysts. Background technique [0002] The operation of nuclear power will produce a large amount of highly radioactive waste - spent fuel, which contains a large amount of unconverted uranium and value-added nuclides, which need to be separated and purified by physical and chemical methods. The Plutonium-Uranium Reduction Extraction (PUREX) process produces a large amount of nitric acid waste liquid containing the reducing agents hydrazine nitrate and hydroxylamine nitrate. During subsequent processing, the nitric acid waste liquor is treated using catalysts to destroy these reducing agents. Since the catalyst supports are mostly adsorption-type porous materials, a certain amount of alpha nuclides will be adsorbed during the treatment process, and the spent catalyst needs to be...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/30G21F9/34
CPCG21F9/304G21F9/34Y02W30/91
Inventor 白杨左臣李保乐郑卫芳晏太红
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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