Glass solidification body of incombustible radioactive waste and synergistic glass solidification method

A technology of radioactive waste and glass solidification, which is used in radioactive purification, glass forming, glass furnace equipment, etc. It can solve the problems of glass fiber and resource waste without considering it, so as to improve the waste containment rate, reduce the processing cost, and make the raw materials easy to use. the effect

Pending Publication Date: 2022-01-28
CHINA NUCLEAR POWER TECH RES INST CO LTD +2
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Problems solved by technology

CN104318971A discloses a glass matrix composition for medium and low-level radioactive glass fibers. The glass matrix composition is melted with radioactive glass fiber waste to form a solidified body. The glass additives used include: SiO 2 , B 2 o 3 、Na 2 O, CaO, Li 2 O, Al 2 o 3 、Ti 2 O, this method is also suitable for radioactive glass fiber waste, but the inventor believes that this combination does not take into account that glass fiber has its own glass-forming characteristics, and only treats it as waste, which is a waste of resources

Method used

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  • Glass solidification body of incombustible radioactive waste and synergistic glass solidification method
  • Glass solidification body of incombustible radioactive waste and synergistic glass solidification method
  • Glass solidification body of incombustible radioactive waste and synergistic glass solidification method

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Experimental program
Comparison scheme
Effect test

Embodiment 1

[0188] Embodiment 1. Waste source item component test

[0189] The oxide composition of the waste source item plays a vital role in the glass formulation design, which directly affects the applicability of the formulation and the performance of the cured body, and the overall consideration of the oxide composition in radioactive waste. Using X-ray fluorescence spectrometer (XRF, PANalytical.B.V, Zetium) and full-spectrum direct-reading plasma emission spectrometer (ICP-OES, LEEMAN LABS, Prodigy) to test the composition of non-combustible waste (glass fiber, soil, concrete), radioactivity Nuclides mainly consider fission products 137 Cs, 90 Sr and activation products 60 Co.

[0190] The waste sources used in the specific examples include fiberglass, soil, and concrete. The test results are shown in Table 1.

[0191] Table 1. Main oxide components of non-radioactive waste (glass fiber, soil, concrete)

[0192] Element glass fiber soil concrete SiO 2

...

Embodiment 2

[0195] Embodiment 2. Preparation of glass fiber+concrete non-combustible waste (binary combination) hybrid glass solidified body

[0196] 2.1 Preparation of glass solidified body

[0197] (1) Pretreatment: The large-volume glass fiber in the non-combustible radioactive waste is crushed or sheared, and the soil is dried to facilitate the accuracy of the measurement results.

[0198] (2) Ingredients (preparation of the mixture to be melted): Weigh 70wt% of glass fiber, 25wt% of concrete, and the weight of non-combustible waste accounts for 95wt% of the mixture to be melted. Weigh glass additive Na 2 O is used as a glass matrix composition, and the weight ratio in the mixture to be melted is 5wt%, and Na 2 O to Na 2 CO 3 Form introduction. Weigh 0.2wt% of CoO and 0.2wt% of Cs in the glass solidified body 2 O, 0.2 wt% SrO simulated radionuclide. The glass fiber, the concrete, the glass matrix composition and the simulated radionuclide are evenly mixed to obtain the mixture ...

Embodiment 3

[0224] Example 3. Preparation of Soil+Concrete Vitrified Body as a Binary Combination Waste Source

[0225] 3.1. Preparation of glass solidified body

[0226] (1) Pretreatment: The large volume of concrete in the non-combustible radioactive waste is crushed or sheared so that the maximum size of the concrete raw material does not exceed 2mm, and the soil drying treatment facilitates the accuracy of the measurement results.

[0227] (2) Ingredients (preparation of the mixture to be melted): 50wt% of concrete and 40wt% of soil are weighed, and the weight of non-combustible waste accounts for 90wt% of the mixture to be melted. Weigh glass additive B 2 o 3 As a glass matrix composition, the weight proportion in the mixture to be melted is 10wt%, B 2 o 3 with H 3 BO 3 Form introduction. Weigh 0.2wt% of CoO and 0.2wt% of Cs in the glass solidified body 2 O, 0.2 wt% SrO simulated radionuclide. The concrete, the soil, the glass matrix composition and the simulated radionuclid...

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Abstract

The invention relates to a glass solidification body of incombustible radioactive waste and a synergistic glass solidification method. The raw materials of the glass solidified body are derived from non-combustible wastes such as radioactive glass fibers, soil, concrete and the like, and the glass fibers, the soil and the concrete can be arbitrarily combined into two elements and three elements according to actual conditions. A used glass substrate is simple in composition and small in dosage. The glass solidified body obtained through synergistic glass solidification has high chemical stability, the leaching resistance rate, the compressive strength, the impact resistance and the like all meet the geological disposal requirements, the waste containing capacity is high, the obvious volume reduction effect is achieved, and the follow-up landfill cost can be reduced.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste treatment, and in particular relates to a vitrification body of incombustible radioactive solid waste and a method for synergistic vitrification. Background technique [0002] With the development of nuclear energy technology, the problem of nuclear pollution has been brought along, and the treatment of radioactive waste has attracted more and more attention. At present, nuclear power plants mainly adopt the method of cement solidification to treat solid waste. The solidified body produced by this method has a high leaching rate, a large volume expansion ratio, and high follow-up treatment costs. Compared with it, the vitrified body has better chemical stability, smaller volume expansion ratio, and higher waste containment rate, and is an effective alternative for treating radioactive solid waste. [0003] CN112382429A discloses a method for synergistic vitrification of medium and low-l...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C03C14/00C03B19/02C03B5/235G21F9/16G21F9/30
CPCC03C14/00C03B5/235C03B19/02G21F9/162G21F9/305
Inventor 李丽丽林鹏李坤锋文炎立刘春雨杜颖哲刘晓伟周江刘夏杰李利
Owner CHINA NUCLEAR POWER TECH RES INST CO LTD
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