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

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...

AI Technical Summary

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 solidification, which eventually leads to a high leaching rate;

[0009] (2) Retained nuclides in alkali slag cement solidified materials 90 Sr, 137 Cs has strong ability, but its mechanical properties and fluctuations are large, the setting time is short, there is no national standard, and its application is limited

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