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Borosilicate glass ceramic curing base material, and preparation method and application thereof

A technology for solidifying borosilicate glass and ceramics, used in radioactive purification, nuclear engineering, etc., can solve the problems of lack of long-term safety and stability evaluation methods for glass solidified bodies, low containment capacity and low containment capacity of nuclear waste solidified bodies, etc. Achieve the effect of improving chemical stability and packaging capacity, minimizing volume, and effectively containing

Inactive Publication Date: 2020-04-07
CHINA BUILDING MATERIALS ACAD
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] Vitrification is currently the best measure for the solidification of high-level radioactive waste in the nuclear industry. Nuclides exist in glass in the form of network extraction, but some nuclides are affected by solubility and have low containment capacity, which directly leads to low containment capacity of nuclear waste solidification. , and the vitrified body lacks a long-term safety and stability evaluation method, and its safety has been questioned

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  • Borosilicate glass ceramic curing base material, and preparation method and application thereof
  • Borosilicate glass ceramic curing base material, and preparation method and application thereof

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Embodiment 1

[0036] This embodiment provides a method for preparing a borosilicate glass ceramic solidified substrate, which specifically includes the following steps:

[0037] (1) select the raw material of borosilicate glass-ceramic solidified base material, by mass percentage, described raw material comprises the following components: SiO 2 50%, B 2 o 3 11%, Na 2 O 13%, CaO 5%, TiO 2 10%, ZrO 2 4%, CeO 2 5%, CaF 2 1%, Cr 2 o 3 1%;

[0038] (2) Put the raw materials into a mixer and grind them thoroughly; place them in a high-temperature furnace and melt them at 1250°C for 3 hours to completely melt the ingredients into a liquid melt; the particle size of the grinding is no more than 40 head;

[0039] (3) Pour the liquid melt into a mold preheated at 500°C, cool and shape it, put it in an annealing furnace at 530°C for 2 hours, and cool to room temperature with the furnace to obtain a silicate glass ceramic solidified substrate .

Embodiment 2

[0041] This embodiment provides a method for preparing a borosilicate glass ceramic solidified substrate, which specifically includes the following steps:

[0042] (1) select the raw material of borosilicate glass-ceramic solidified base material, by mass percentage, described raw material comprises the following components: SiO 2 53%, B 2 o 3 10%, Na 2 O 10%, CaO 7%, TiO 2 11%, ZrO 2 4%, CeO 2 4%, CaF 2 0.5%, Fe 2 o 3 2.5%;

[0043] (2) Put the raw materials into a mixer and grind them thoroughly; place them in a high-temperature furnace and melt them at 1270°C for 3.5 hours to completely melt the ingredients into a liquid melt; the particle size of the grinding is no more than 40 head;

[0044] (3) The liquid melt is poured into a preheated mold at 510°C, cooled and molded, placed in an annealing furnace at 530°C for 2.5 hours, and cooled to room temperature with the furnace to obtain a silicate glass ceramic solidified substrate .

Embodiment 3

[0046] This embodiment provides a method for preparing a borosilicate glass ceramic solidified substrate, which specifically includes the following steps:

[0047] (1) select the raw material of borosilicate glass-ceramic solidified base material, by mass percentage, described raw material comprises the following components: SiO 2 47%, B 2 o 3 12%, Na 2 O 14%, CaO 4%, TiO 2 10%, ZrO 2 6%, CeO 2 4%, CaF 2 0.5%, P 2 o 5 1%;

[0048] (2) Put the raw materials into a mixer and grind them thoroughly; place them in a high-temperature furnace and melt them at 1200°C for 4 hours to completely melt the ingredients into a liquid melt; the particle size of the grinding is no more than 40 head;

[0049] (3) Pour the liquid melt into a mold preheated at 500°C, cool and form it, put it in an annealing furnace at 550°C for 2 hours, and cool to room temperature with the furnace to obtain a silicate glass ceramic solidified substrate .

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Abstract

The invention relates-a borosilicate glass ceramic curing base material, and a preparation method and an application thereof. The borosilicate glass ceramic curing base material comprises, by mass, 47-65% of SiO2, 8-15% of B2O3, 10-15% of Na2O, 4-10% of CaO, 8-13% of TiO2, 4-6% of ZrO2, 0.5-10% of CeO2, 0-2.5% of CaF2, 0-2.5% of Cr2O3, 0-2.5% of P2O5 and 0-2.5% of Fe2O3. The borosilicate glass ceramic curing base material has a simple preparation process and can be widely applied to curing treatment of high-level nuclear wastes. The multi-component curing base material is adopted, and variousradionuclides can be cured at the same time by adjusting the composition and content of the curing base material and adjusting the melting process; and radioactive nuclide is confined in a crystal structure, so actinide elements in the high-level radioactive wastes can be effectively cured, and the chemical stability and the package capacity of nuclear wastes in a cured body are greatly improved.

Description

technical field [0001] The invention belongs to the field of treatment and disposal of radioactive nuclear waste, and in particular relates to a borosilicate glass ceramic solidified base material and its preparation method and application. Background technique [0002] High-level radioactive waste mainly refers to the high-level radioactive waste liquid and its solidified body produced by the reprocessing of spent fuel, spent fuel to be disposed of directly (one-pass type), and other wastes with corresponding radioactive levels. Although the volume of high-level radioactive waste is less than 1% of the volume of radioactive waste produced by the nuclear fuel cycle, the amount of radioactivity contained in it exceeds 99% of the total radioactive amount of the nuclear fuel cycle. High-level radioactive waste contains neptunium, plutonium, americium, technetium, iodine, strontium, cesium and other radionuclides, and its main characteristics are long duration of radioactivity, ...

Claims

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Application Information

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IPC IPC(8): G21F9/16C03C10/00
CPCC03C10/0009G21F9/162
Inventor 朱永昌邢庆立崔竹韩勖于雷赵崇
Owner CHINA BUILDING MATERIALS ACAD
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