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Preparation method of borosilicate glass ceramic solidified body containing uranpyrochlore

A borosilicate glass and ceramic solidification technology, which is applied in the field of radioactive waste treatment, can solve the problems of limited containment capacity, limited proportion of ceramic phase, and the inability of the solidified body to handle high-level radioactive waste to the greatest extent, so as to increase the containment capacity, The effect of uniform distribution of ceramic phase and compact structure

Inactive Publication Date: 2019-05-17
SOUTHWEAT UNIV OF SCI & TECH
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

At present, the journal "Atomic Energy Science and Technology" published the article "The influence of preparation technology on the structure and properties of uranium pyrochlore-based glass-ceramic solidified body". Ceramic solidified body, although the melting-heat treatment method combined with pre-sintering and ball milling can reduce the composition of nuclide U remaining in the glass phase and improve the composition of nuclide U in the ceramic phase, but this method still has the following Problem: The proportion of the ceramic phase in the entire solidified body is limited, otherwise it will affect the strength of the solidified body, which limits the containment capacity of the ceramic relative to the nuclide U, so that the solidified body cannot handle high-level radioactive waste to the greatest extent

Method used

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  • Preparation method of borosilicate glass ceramic solidified body containing uranpyrochlore
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  • Preparation method of borosilicate glass ceramic solidified body containing uranpyrochlore

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Embodiment 1

[0035] A method for preparing a borosilicate glass ceramic solidified body containing uranium pyrochlore in this embodiment, step 1, weighing the following components by weight percentage: SiO 2 20.5%, Al 2 o 3 4%, Na 2 CO 3 9%, B 2 o 3 4%, CaF 2 17.5%, CaO4%, U 3 o 8 25.5%, TiO 2 15%;

[0036] Step 2. Pretreatment of glass-ceramic raw materials

[0037] SiO 2 、Al2 o 3 、Na 2 CO 3 , B 2 o 3 , CaF 2 Wet-mix and dry the six components of CaO to obtain a uniformly mixed first mixture, and U 3 o 8 and TiO 2 The two components were wet-mixed and dried to obtain a uniformly mixed second mixture. The first mixture and the second mixture were respectively sintered at 650° C. for 1 h under an argon atmosphere, and then the sintered first mixture and The second mixture is ball milled for 3 hours respectively, the first mixture after ball milling is the first glass-ceramic raw material, and the second mixture after ball-milling is the second glass-ceramic raw material...

Embodiment 2

[0048] A method for preparing a borosilicate glass ceramic solidified body containing uranium pyrochlore in this embodiment, step 1, weighing the following components by weight percentage: SiO 2 20%, Al 2 o 3 2%, Na 2 CO 3 8%, B 2 o 3 3%, CaF 2 17%, CaO3%, U 3 o 8 30%, TiO 2 16%;

[0049] Step 2. Pretreatment of glass-ceramic raw materials

[0050] SiO 2 、Al 2 o 3 、Na 2 CO 3 , B 2 o 3 , CaF 2 Wet-mix and dry the six components of CaO to obtain a uniformly mixed first mixture, and U 3 o 8 and TiO 2 The two components were wet mixed and dried to obtain a uniformly mixed second mixture. The first mixture and the second mixture were respectively sintered at 750° C. for 3 hours under an argon atmosphere, and then the sintered first mixture and The second mixture is ball milled for 4 hours respectively, the first mixture after ball milling is the first glass-ceramic raw material, and the second mixture after ball-milling is the second glass-ceramic raw material...

Embodiment 3

[0066] A method for preparing a borosilicate glass ceramic solidified body containing uranium pyrochlore in this embodiment, step 1, weighing the following components by weight percentage: SiO 2 23.5%, Al 2 o 3 2.1%, Na 2 CO 3 8.1%, B 2 o 3 3.1%, CaF 2 20%, CaO3.1%, U 3 o 8 20.1%, TiO 2 20%;

[0067] Step 2. Pretreatment of glass-ceramic raw materials

[0068] SiO 2 、Al 2 o 3 、Na 2 CO 3 , B 2 o 3 , CaF 2 Wet-mix and dry the six components of CaO to obtain a uniformly mixed first mixture, and U 3 o 8 and TiO 2 The two components were wet-mixed and dried to obtain a uniformly mixed second mixture. The first mixture and the second mixture were respectively sintered at 700° C. for 2 hours under an argon atmosphere, and then the sintered first mixture and The second mixture is ball milled for 3.5 hours respectively, the first mixture after ball milling is the first glass-ceramic raw material, and the second mixture after ball-milling is the second glass-cerami...

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Abstract

The invention relates to the technical field of radioactive waste treatment, in particular to a preparation method of a borosilicate glass ceramic solidified body containing uranpyrochlore. The preparation method comprises the following steps of respectively performing wet mixing drying and pre-sintering, gradual melting, sintering and quenching with SiO2, Al2O3, Na2CO3, B2O3, CaF2, CaO, U3O8 andTiO2 as raw materials to prepare the borosilicate glass ceramic solidified body. The preparation method has the advantages that the crystallization rate of the uranpyrochlore in glass can be regulatedand controlled; the ingredients remained by nuclide in the glass phase can be reduced; the accommodating capacity of nuclide U in the ceramic phase can be improved; the accommodating capacity of thenuclide U in the whole solidified body can be improved; the prepared borosilicate glass ceramic solidified body containing uranpyrochlore has the advantages of uniform crystal grain distribution, hightissue compactness and high intensity.

Description

technical field [0001] The invention relates to the technical field of radioactive waste treatment, in particular to a method for preparing a solidified body of borosilicate glass ceramics containing uranium pyrochlore. Background technique [0002] In the reprocessing process of spent fuel with co-decontamination of uranium and plutonium, high-level radioactive wastes (High-Level Radioactive Wastes, HLWs) will be produced. HLWs are highly radioactive, highly toxic, and have a high heating rate. If HLWs are released into the environment, it will Great harm to the environment. [0003] In the prior art, there are ways to vitrify HLLW (high-level radioactive waste) or to solidify HLLW ceramics to process HLLW, but HLLW vitrification has low containment capacity for actinide nuclides (≤0.4wt.%) and poor long-term stability (Easy phase separation and water-soluble yellow phase) and other problems, resulting in the development of large-scale production of HLLW vitrification; HLL...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C03C10/16C03C6/06
Inventor 谢华冯志强王烈林
Owner SOUTHWEAT UNIV OF SCI & TECH
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