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Glass solidifying body for halide radioactive waste and preparation method thereof

A radioactive waste and vitrification technology, applied in radioactive purification, nuclear engineering, etc., can solve the problem of small wrapping rate, achieve the effects of increasing wrapping rate, improving chemical stability, and reducing volume

Active Publication Date: 2016-07-06
SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] In order to solve the problem that the encapsulation rate of halide radioactive waste in borosilicate vitrified body is small in the above-mentioned prior art, the present invention aims to provide a kind of halide radioactive waste vitrified body and its preparation method

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0021] Weigh separately (NH 4 )H 2 PO 5 70g, Al(OH) 3 25g, Na 2 CO 3 20g, put each raw material into a mortar and mix well, make a mixed material and put it in a corundum crucible, heat it in a high-temperature furnace at 10°C / min to 1100°C for 2 hours, make a melt, and pour the melt It is molded in a steel mold, and the molded product is kept at a temperature of 450°C for 1 hour, then naturally cooled to room temperature with the furnace, and ground to obtain a vitrified matrix glass powder. 20% by weight of simulated halide-containing radioactive nuclear waste and parent glass powder are mixed evenly in proportion, heated at 10°C / min to 1000°C for 1 hour, and the melt is poured into a mold for molding, and sodium aluminum is produced Phosphorous system glass is a solidified glass body of halide-containing radioactive nuclear waste.

Embodiment 2

[0023] Weigh separately (NH 4 )H 2 PO 4 60g, Al(OH) 3 15g, Na 2 CO 3 12g, Fe 2 o 3 10g, put each raw material into a mortar and mix well to make a mixed material, place it in a corundum crucible, heat it in a high-temperature furnace at 10°C / min to 1000°C for 1 hour, make a melt, and pour the melt It is molded in a steel mold, and the molded product is kept at a temperature of 400°C for 5 hours, then naturally cooled to room temperature with the furnace, and ground to obtain a vitrified matrix glass powder. 30% by weight of simulated halide-containing radioactive nuclear waste and parent glass powder are fully mixed in proportion, heated at 10°C / min to 900°C for 2 hours, and the melt is poured into a mold for molding, and sodium aluminum is produced Phosphorous system glass is a solidified glass body of halide-containing radioactive nuclear waste.

Embodiment 3

[0025] Weigh separately (NH 4 ) 2 HPO 4 55g, Al 2 o 3 30g, Na 2 CO 3 8g, Fe 2 o 3 20g, PbO8g, put each raw material into a mortar and mix well, make a mixed material and place it in a corundum crucible, heat it in a high-temperature furnace at 10°C / min to 1200°C for 2 hours, and make a melt. The body is poured into a steel mold for molding, and the molded object is kept at a temperature of 500°C for 1 hour, and then naturally cooled to room temperature with the furnace, and the vitrified body matrix glass powder is obtained after grinding. 10% by weight of the simulated halide-containing radioactive nuclear waste and the mother glass powder are fully mixed in proportion, heated at 10°C / min to 1100°C for 2 hours, and the melt is poured into a mold for molding, and sodium aluminum is produced Phosphorous system glass is a solidified glass body of halide-containing radioactive nuclear waste.

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PUM

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Abstract

The invention relates to a preparation method of a glass solidifying body for halide radioactive waste.The method comprises the steps that 1, 55%-75% by weight of phosphorous compound, 15%-30% by weight of aluminiferous compound, 10%-30% by weight of sodium carbonate, 0-20% by weight of ferruginous compound and 0-30% by weight of leady compound are mixed, and powdered glass is formed; 2, 10%-30% by weight of the halide radioactive waste and 70%-90% by weight of the powdered glass are mixed, and the glass solidifying body is formed.The invention further provides the glass solidifying body for the halide radioactive waste.The glass solidifying body is used for solidifying the halide radioactive waste rich in fluorides, chlorides and the like through a sodium and aluminum phosphate system, therefore, the wrapping rate of the glass solidifying body to the halide radioactive waste is greatly increased, and the volume of the waste solidifying body is reduced.

Description

technical field [0001] The invention relates to vitrification, in particular to a vitrified body of halide radioactive waste and a preparation method thereof. Background technique [0002] With the in-depth study of advanced nuclear fuel cycle methods, dry reprocessing of spent fuel has attracted more and more attention in recent years. In the process of dry reprocessing of spent fuel, halides are mostly selected as diluents, and molten salt wastes containing metal halides are often produced, such as high-level radioactive wastes produced by high-temperature chemical treatment of Pu metals containing CsCl and SrF 2 Wait. Molten salt reactors use molten fluoride mixed salt as the main coolant, and even the fuel itself is dissolved in fluoride high-temperature molten salt. Various types of fluorine-containing radioactive waste are produced. Fluorine-containing radioactive wastes are mostly corrosive, poor chemical stability, easy to deliquescence, and low melting point. Hig...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/00G21F9/34C03C3/17
CPCC03C3/17G21F9/00G21F9/34
Inventor 乔延波马洪军孙亚平刘学阳钱正华王帅陈堃
Owner SHANGHAI INST OF APPLIED PHYSICS - CHINESE ACAD OF SCI
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