Treatment method of radioactive solid waste

A treatment method and technology for solid waste, applied in radioactive purification, nuclear engineering, etc., can solve the problems of low strength, low durability of solidified body, and a large amount of addition, and achieve a strong applicability, good stability, and wide compatibility. Effect

Active Publication Date: 2020-05-12
NANHUA UNIV
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  • Abstract
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Problems solved by technology

[0011] However, in the current solidification methods for medium and low-level radioactive waste, the solidified body has low durability and low strength; the effect of adsorbing solid waste is not satisfactory, and the waste residue cannot be fully utilized.
Moreover, most of the current methods need to add a large amount of water and other admixtures
In addition, the curing effect of many resource recovery methods is unstable, which will lead to the re-release of radioactive elements (ions), and does not have strong adaptability

Method used

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  • Treatment method of radioactive solid waste

Examples

Experimental program
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Effect test

Embodiment 1

[0060] In this embodiment, the slag of a certain uranium mine waste dump in Hunan is taken as a sample.

[0061] Process the sample according to the following steps to obtain a cured body:

[0062] (1) Crushing: Use a jaw crusher to crush the slag to a particle size of 0-5 mm, which is a continuous gradation without screening.

[0063] (2) Preparation of mixed acid: use industrial sulfuric acid to dilute to a concentration of 75% dilute sulfuric acid; select industrial phosphoric acid to dilute to a concentration of 75% dilute phosphoric acid; dilute sulfuric acid according to the proportion: dilute phosphoric acid=8.8:1.2 to prepare mixed acid .

[0064] (3) Quenching and tempering: select brand LGY402, liquid sodium silicate (water glass) whose modulus is 3.20~3.40 for use, its technical parameters are as shown in Table 1; under stirring conditions, water glass by mass ratio: mixed acid = 85:15 mixed to obtain modified water glass.

[0065] Table 1 technical parameters of...

Embodiment 2

[0075] In this embodiment, the leaching slag of a uranium ore wet smelting plant in Hunan is taken as a sample, the particle size of the sample is 0-1.0mm, and the water content is 8%-15%.

[0076] Process the sample according to the following steps to obtain a cured body:

[0077] (1) Crushing: Dry the sample until the water content is less than 5%, and then crush and disperse the leached slag with a hammer crusher.

[0078] (2) preparation mixed acid: same as embodiment 1.

[0079] (3) Quenching and tempering: select brand LGY403, liquid sodium silicate (water glass) whose modulus is 3.20~3.40 for use, its technical parameters are as shown in Table 1; under stirring conditions, water glass by mass ratio: mixed acid = 88:12 mixed to obtain modified water glass.

[0080] (4) Preparation of admixtures: select FeSi65 ferrosilicon powder and bentonite, steel slag powder, and fly ash as blending raw materials, and the particle size of the blended raw materials is -0.045mm, 100%;...

Embodiment 3

[0088] In this embodiment, vanadium slag from a certain shale vanadium mine in Hunan is taken as a sample. The particle size of the sample is 0-12mm. The uranium content is 0.01%wt and the moisture content is 3%-4%.

[0089] Process the sample according to the following steps to obtain a cured body:

[0090] (1) Crushing: use a hammer crusher to crush the slag to a particle size of 0-2 mm, which is a continuous gradation without screening.

[0091] (2) preparation mixed acid: same as embodiment 1.

[0092] (3) Refined and tempered: the same as in Example 2.

[0093] (4) Preparation of admixture: use 100% reduced iron powder, silica fume, fly ash, and granulated blast furnace slag powder with a particle size of -0.045mm as the blending raw material, according to reduced iron powder: silica fume: fly ash : The ratio of granulated blast furnace slag powder = 1:2:3:4 is used as admixture.

[0094] (5) Prepare batching material: select the liquid sodium hydroxide of IL-II grade ...

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Abstract

The invention provides a radioactive solid waste treatment method which comprises the following steps: a) crushing radioactive solid waste to be treated, and mixing the crushed radioactive solid wastewith an admixture, sodium hydroxide and modified water glass to obtain a mixture; wherein the modified water glass is prepared by tempering water glass and inorganic mixed acid; and the inorganic mixed acid is prepared from sulfuric acid and phosphoric acid; and b) molding the mixture obtained in the step a) to obtain a solidified body. Compared with the prior art, the treatment method provided by the invention has the advantages of no need of moisturizing maintenance, no secondary pollution, no sewage discharge, no waste gas, no new solid waste, wide compatibility and strong applicability; the obtained solidified body has the characteristics of high strength and good stability, the requirements of GB 14569.1 Low and Medium Level Radioactive Solidified Body Performance Requirements-CementSolidified Body are met, and the solidified body solid waste package can meet the requirements of the near-surface disposal standard of radioactive solid waste in China.

Description

technical field [0001] The invention relates to the technical field of environmental protection, in particular to a method for treating radioactive solid waste. Background technique [0002] At present, the treatment methods of radioactive waste mainly include cement solidification, asphalt solidification, plastic solidification, glass solidification and artificial rock solidification. The treatment methods for high-level radioactive waste (HLW) mainly include vitrification and artificial rock solidification, and the treatment methods for intermediate and low-level radioactive waste (ILLW) generally include asphalt solidification, cement solidification, plastic solidification and other solidification. [0003] (1) Asphalt curing: [0004] Asphalt solidification was first proposed by Belgium in 1960, and countries such as France, West Germany, the United States, and the former Soviet Union began research on asphalt solidification. In our country, the research on asphalt cur...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/30G21F9/34
CPCG21F9/305G21F9/34
Inventor 蒋复量刘永罗明亮吴浩楠李向阳洪昌寿王者谭彪
Owner NANHUA UNIV
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