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High-temperature self-propagating curing method for strontium-containing radioactive graphite

A technology of high-temperature self-propagation and solidification method, which is applied in the field of radioactive graphite to achieve the effects of good repeatability, simple technical operation and high production efficiency

Inactive Publication Date: 2012-08-01
SOUTHWEAT UNIV OF SCI & TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, there are no relevant reports at home and abroad on the use of high-temperature self-propagating technology for the treatment of radioactive graphite.

Method used

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Examples

Experimental program
Comparison scheme
Effect test

example 1

[0013] Example 1. Graphite, titanium and strontium-containing radioactive graphite (the molar percentage of strontium is 20%) are used as raw materials. Adjust the formula so that the molar ratio of the total amount of graphite to titanium is 0.8:1.2, and the molar ratio of titanium to strontium is 1:0.25. According to the ratio of raw materials to grinding balls of 1:2, zirconium dioxide (ZrO 2 ) balls, and dry milled in a ball mill for 10 hrs in a ball mill. Then, under a pressure of 10 MPa, the mixed and finely processed raw materials were pre-pressed into discs with a diameter of 13 mm. The molded sample was ignited by tungsten wire at ~2200 °C, and the sample was cooled to room temperature after self-combustion to obtain a solidified body of strontium-containing radioactive graphite.

example 2

[0014] Example 2. Graphite, titanium and strontium-containing radioactive graphite (the molar percentage of strontium is 10%) are used as raw materials. Adjust the formula so that the molar ratio of graphite to titanium is 0.8:1.2, and the molar ratio of titanium to strontium is 1:0.1. According to the ratio of raw materials to grinding balls of 1:2.5, zirconium dioxide (ZrO 2 ) balls, and dry milled in a ball mill for 5 hrs in a ball mill. Then, under a pressure of 12 MPa, the mixed and finely processed raw materials were pre-pressed into discs with a diameter of 13 mm. A tungsten wire is used to ignite the molded sample at ~2500 °C, and the sample is cooled to room temperature after self-combustion to obtain a solidified body of strontium-containing radioactive graphite.

example 3

[0015] Example 3. Graphite, titanium and strontium-containing radioactive graphite (the molar percentage of strontium is 30%) are used as raw materials. Adjust the formula so that the molar ratio of graphite to titanium is 1:1, and the molar ratio of titanium to strontium is 1:0.25. According to the ratio of raw materials to grinding balls of 1:2, zirconium dioxide (ZrO 2 ) balls and dry-milled in a ball mill for 7 hrs in a ball mill. Then, under a pressure of 10 MPa, the mixed and finely processed raw materials were pre-pressed into discs with a diameter of 13 mm. The molded sample was ignited by chemical ignition (ignition temperature ~ 2800 ℃), and the sample was ignited by itself and cooled to room temperature to obtain a solidified body of strontium-containing radioactive graphite.

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Abstract

The invention discloses a high-temperature self-propagating curing method for strontium-containing radioactive graphite. The method comprises the following steps of: firstly, analyzing compositions and content of the strontium-containing radioactive graphite; secondly, designing a cured body formulation by using graphite, titanium and the strontium-containing radioactive graphite as raw materials; thirdly, mixing, refining and pre-pressing the raw materials; fourthly, igniting a molded sample at the temperature of between 1,500 and 3,000DEG C; and finally, obtaining a strontium-containing radioactive graphite cured body to realize the curing. The high-temperature self-propagating curing method is simple in operation, high in working efficiency and high in repeatability, and can be widely applied to large-scale disposal of strontium-containing radioactive nuclear graphite discharged by nuclear power plants and the like.

Description

technical field [0001] This patent relates to graphite, in particular to a treatment method for radioactive graphite. Background technique [0002] Certain radioactive wastes are inevitably produced during the operation of the nuclear industry. If these radioactive wastes are not treated and disposed of safely and effectively, it will not only affect and restrict the sustainable development of the nuclear industry, but also endanger human beings. continue. In particular, the Fukushima nuclear accident in Japan not long ago has once again aroused great concern for human beings about radioactive harmful substances. [0003] There are currently relatively good measures for the treatment and disposal of low- and medium-level radioactive waste, but the treatment of high-level radioactive waste has not been well resolved. At present, the research on high-level radioactive waste treatment technology mainly focuses on high-temperature solid-state reaction method, mechanical ball m...

Claims

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Application Information

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IPC IPC(8): G21F9/34
Inventor 易发成卢喜瑞陈梦君崔春龙唐敬友段涛王哲
Owner SOUTHWEAT UNIV OF SCI & TECH
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