High-salt high-alkali Medium-low-level radioactive liquid waste cement solidified body and preparation method thereof

A technology for curing radioactive waste liquid and cement, which is applied in the field of solidification treatment and radioactive waste disposal. It can solve problems such as easy bleeding, high leaching rate, and short coagulation time, so as to reduce the generation of microcracks, reduce the heat of hydration, The effect of increasing retention capacity

Inactive Publication Date: 2011-08-31
SOUTHWEAT UNIV OF SCI & TECH
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Problems solved by technology

[0008] (1) The curing of high-salt, high-alkali, medium and low-level radioactive waste liquid has its particularity. If the formula of the solidified body is not suitable, it may be difficult to guarantee the long-term strength of the solidified body; Insufficient water, etc., resulting in uneven solidifi

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  • High-salt high-alkali Medium-low-level radioactive liquid waste cement solidified body and preparation method thereof

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Embodiment 1

[0039] A high-salt, high-alkali, medium-low level radioactive waste cement solidified body and a preparation method thereof, comprising:

[0040] According to the ratio of 42.5 grade low-heat Portland cement: slag powder: fly ash: zeolite: attapulgite (palygorskite) = 40wt.%: 20wt.%: 20wt.%: 10wt.%: 10wt.% (wt .% is the mass percentage, the same below) Weigh the materials and mix them to make the curing material. Based on the curing material, weigh 0.1% cellulose ether, 1.0% (in which Na 2 O meter) water glass with a modulus of 2.5 to 3.5 were placed in the same container. According to the ratio of medium and low-level radioactive waste liquid with a salt content of 200g / L and a pH value > 14: solidified material (hereinafter referred to as the liquid-solid ratio) = 0.65, measure the radioactive waste liquid; take the radioactive waste liquid and add it to the above container Stir in a container with curing material, water glass, and cellulose ether for 10 minutes to obtain ...

Embodiment 2

[0042] A high-salt, high-alkali, medium-low level radioactive waste cement solidified body and a preparation method thereof, comprising:

[0043] Weigh the material according to the ratio of 42.5 grade low-heat Portland cement: slag powder: fly ash: zeolite: attapulgite (palygorskite) = 30wt.%: 40wt.%: 15wt.%: 10wt.%: 5wt.% , mixed to make a curing compound. Based on the cured material, weigh 2.5% (based on the Na 2 O meter) water glass with a modulus of 2.5 to 3.5 and 0.1% cellulose ether were placed in the same container. According to the ratio of medium and low-level radioactive waste liquid with a salt content of 300g / L and a pH value > 14: solidified material (hereinafter referred to as the liquid-solid ratio) = 0.65, measure the radioactive waste liquid; take the radioactive waste liquid and add it to the above container Stir in a container with curing material, water glass, and cellulose ether for 10 minutes to obtain a uniform mixed slurry. The fluidity of the mixed...

Embodiment 3

[0045] A high-salt, high-alkali, medium-low level radioactive waste cement solidified body and a preparation method thereof, comprising:

[0046] a. Ingredients: High-salt, high-alkali, medium-low level radioactive waste liquid and solidified material in the ratio of high-salt, high-alkali, medium-low level radioactive waste liquid: solidified material = 0.75:1 by mass ratio, and the modulus is 2.5-3.5. Na in water glass 2 The water glass of solidified material quality 3% of O meter, gets the cellulose ether of solidified material quality 0.5%;

[0047] The components and mass percentages of the curing material include: 40% low-heat Portland cement, 15% slag powder, 30% fly ash, 5% zeolite, and 10% attapulgite, which are taken according to the mass percentage each component;

[0048] b. Preparation of cured body: put the components of the cured material described in step a, water glass, and cellulose ether in a (specific) container, and then add the high-salt, high-alkali, m...

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Abstract

The invention discloses a high-salt high-alkali medium-low-level radioactive liquid waste cement solidified body which is composed by mixing the following components: high-salt high-alkali medium-low-level radioactive liquid waste and, solidification material, water glass and cellulose ether, wherein the high-salt high-alkali medium-low-level radioactive liquid waste to the solidification material is 0.55-0.75: 1 in mass proportion; the modulus of the water glass is 2.5-3.5 based on Na2O in the water glass and the mass of the solidification material is 1-3% of the mass of the water glass ; the mass of the solidification material is 0.05-0.5% of the mass of the cellulose ether; the component mass percent of the solidification material is as follows: 20-40% of low-heat Portland cement, 15-50% of slag powder, 15-30% of coal ash, 5-15% of zeolite and 5-15% of attapulgite; and the cement solidification body with various properties meeting the requirements is obtained by carrying out normal-temperature maintenance on the mixed slurry which obtained by mixing and stirring. The high-salt high-alkali medium-low-level radioactive liquid waste cement solidified body is suitable for the solidification of the medium-low-level radioactive liquid waste, which has the total salt concentration being 100-400g/L, the pH value being larger than 13 and the nuclide being 90Sr or/and 137 Cs.

Description

technical field [0001] The invention belongs to radioactive waste disposal and solidification treatment, and relates to a high-salt, high-alkali, medium-low level radioactive waste liquid cement solidified body and a preparation method thereof. Especially suitable for the total salt concentration of 100 ~ 400g / L, its pH value > 13, and the main ion contained is Na + , AlO 2 － , NO 3 － , CO 3 2－ 、PO 4 3－ , SO 4 2－ , or / and OH － and nuclides 90 Sr or / and 137 Solidification treatment of medium and low level radioactive waste liquid of Cs. Background technique [0002] The radioactive waste produced by nuclear fuel reprocessing, various nuclear reactors, nuclear power plants and other devices is quite harmful and cannot be discharged directly to the environment. It must be solidified by a suitable method and stored in isolation by an appropriate device until the radioactive elements in it decay. until there is no harm to the environment. At present, the solidif...

Claims

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Application Information

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IPC IPC(8): G21F9/20G21F9/06G21F9/16
Inventor 李玉香易发成陈雅斓肖正学袁燕秋
Owner SOUTHWEAT UNIV OF SCI & TECH
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