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Boron-containing waste liquid cement curing formula and curing method

A technology of concentrated waste liquid and cement solidification, which is applied in the fields of radioactive purification and nuclear engineering, can solve the problems of low waste containment rate and high nuclide leaching rate, and achieve the goal of reducing radionuclide leaching rate and meeting the requirements of automatic loading and unloading Effect

Pending Publication Date: 2021-07-02
CNNC NUCLEAR POWER OPERATION MANAGEMENT +1
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  • Abstract
  • Description
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  • Application Information

AI Technical Summary

Problems solved by technology

[0005] Based on this, it is necessary to provide a boron-containing concentrated waste liquid cement solidification solution for the problems of high nuclide leaching rate, low waste inclusion rate and no local bulk cement supply in the existing concentrated waste cement solidification formula. Formulation and curing method

Method used

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  • Boron-containing waste liquid cement curing formula and curing method
  • Boron-containing waste liquid cement curing formula and curing method

Examples

Experimental program
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Effect test

Embodiment 1

[0044] A boron-containing concentrated waste liquid cement solidification formula, comprising ordinary Portland cement, lime, additives, molecular sieves, concentrated waste liquid and calcium chloride, the ordinary Portland cement, lime, concentrated waste liquid, additives, molecular sieves and The mass ratio of calcium chloride is 1:0.174:0.696:0.01:0.02:0.005.

[0045] The strength grade of the ordinary Portland cement is 42.5, 3-day compressive strength ≥ 17Mpa, 28-day compressive strength ≥ 42.5Mpa, 3-day flexural strength ≥ 3.5Mpa, 28-day flexural strength ≥ 6.5Mpa.

[0046] The ordinary Portland cement comprises the following components in weight percentage: 80%-95% of Portland cement clinker doped with gypsum, and the balance is active materials such as slag, pozzolan, fly ash and limestone.

[0047] The Ca(OH)2 purity in the slaked lime is more than or equal to 95%.

[0048] The additive is a water reducer, the water reducer is Glenium C333, and the added amount of ...

Embodiment 2

[0058] A boron-containing concentrated waste liquid cement solidification formula, comprising ordinary Portland cement, lime, additives, molecular sieves, concentrated waste liquid and calcium chloride, the ordinary Portland cement, lime, concentrated waste liquid, additives, molecular sieves and The mass ratio of calcium chloride is 1:0.194:0.787:0.01:0.02:0.005.

[0059] The strength grade of the ordinary Portland cement is 42.5, 3-day compressive strength ≥ 17Mpa, 28-day compressive strength ≥ 42.5Mpa, 3-day flexural strength ≥ 3.5Mpa, 28-day flexural strength ≥ 6.5Mpa.

[0060] The ordinary Portland cement comprises the following components in weight percentage: 80%-95% of Portland cement clinker doped with gypsum, and the balance is active materials such as slag, pozzolan, fly ash and limestone.

[0061] The Ca(OH)2 purity in the slaked lime is more than or equal to 95%.

[0062] The additive is a water reducer, the water reducer is Glenium C333, and the added amount of ...

Embodiment 3

[0072] The boron-containing concentrated waste liquid cement solidification formula of Example 1 is subjected to laboratory cold test verification and thermal test verification to verify whether the formula performance meets GB14569.1 "Performance Requirements for Low and Medium Level Radioactive Waste Solidified Body-Cement Solidified Body" and GB7023 "Long-term leaching test of solidified radioactive waste" requirements.

[0073] 1. Properties of cement slurry: The cement slurry in Example 1 has moderate consistency, low fluidity, and no bleeding after 1 hour.

[0074] 2. Compressive strength: The 28-day compressive strength of the cement solidified body sample should not be less than 7MPa. In this experiment, the cement solidified body of Example 1 was used for the compressive strength test, and the experimental results showed that its 28-day compressive strength was 32.1-43.2 MPa, with an average of 38.5 MPa, meeting the standard requirements.

[0075] 3. Immersion resist...

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Abstract

The present invention particularly relates to a boron-containing waste liquid cement curing formula and a curing method, the boron-containing waste liquid cement curing formula comprises ordinary Portland cement, slaked lime, an additive, a molecular sieve, a concentrated waste liquid and calcium chloride, and the weight ratio of the ordinary Portland cement to the slaked lime to the additive to the molecular sieve to the concentrated waste liquid to the calcium chloride is 1: 0.174-0.194: 0.008-0.012: 0.02: 0.696-0.787: 0.005. The method is suitable for solidifying the boron-containing concentrated waste liquid, and has the following remarkable characteristics that the molecular sieve is added into the formula and is used for adsorbing radionuclides, so that the leaching rate of the radionuclides is reduced; due to the fact that the nuclide leaching rate is reduced, more radioactive concentrated waste liquid can be contained in the unit volume, that is, the solidification volume containing rate of the concentrated waste liquid is increased and reaches 56.93%; PO42.5 cement is adopted as a curing base material, the PO42.5 cement is locally supplied, bulk cement can be provided, and the requirement for automatic loading and unloading of a cement curing system is met.

Description

technical field [0001] The invention belongs to the technical field of nuclear power plant radioactive waste treatment, and in particular relates to a solidification formula of boron-containing concentrated waste liquid cement and a solidification method thereof. Background technique [0002] During the operation of nuclear power plants, a large amount of radioactive waste liquid will be produced. Evaporation and concentration technology is one of the main methods of waste liquid treatment in nuclear power plants. The decontamination factor can reach 10 3 ~10 4 After treatment, most of the nuclides are enriched in the concentrated waste liquid, which must be solidified to facilitate transportation and storage, and then stored in the radioactive solid waste disposal site for a long time to ensure the safe isolation of radioactive solid waste from the environment After 300-500 years of natural decay, radionuclides have reduced their radioactive levels to acceptable levels and...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C04B28/12
CPCC04B28/04G21F9/165C04B2111/00017C04B2201/50C04B2111/00767C04B22/064C04B20/004C04B2103/302C04B22/124C04B22/0046C04B22/0006
Inventor 余达万杨永亮周辰昊郭喜良闫晓俊徐宏明张金朱昌荣谢秀娟刘列姜春辉余达宇欧阳涛赵凯平
Owner CNNC NUCLEAR POWER OPERATION MANAGEMENT
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