CN112700902B - Treatment method of waste graphite crucible - Google Patents

Treatment method of waste graphite crucible Download PDF

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Publication number
CN112700902B
CN112700902B CN202011310352.9A CN202011310352A CN112700902B CN 112700902 B CN112700902 B CN 112700902B CN 202011310352 A CN202011310352 A CN 202011310352A CN 112700902 B CN112700902 B CN 112700902B
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graphite crucible
waste graphite
waste
ashing
pollution
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CN112700902A (en
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王东昱
李玉春
朱勇
董志平
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China North Nuclear Fuel Co Ltd
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China North Nuclear Fuel Co Ltd
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Abstract

The invention belongs to the technical field of radioactive waste treatment, and particularly relates to a treatment method of a waste graphite crucible, which comprises the following steps of firstly, performing source item investigation on a waste graphite crucible pollution layer to determine the pollution depth and the surface pollution degree of the waste graphite crucible; step two, mechanically cutting the inner surface layer of the polluted part of the waste graphite crucible before ashing; and ashing the polluted part, and preserving the non-polluted part. The invention provides a certain technical support for the treatment of the waste graphite crucible pollution layer with fixed model and determined pollution degree; the mechanical separation-ashing and partial ashing are adopted to treat the waste graphite crucible, so that the burning cost and the personnel operation intensity can be effectively reduced, and meanwhile, the non-pollution waste graphite crucible is sold according to the price of high-purity waste graphite, the treatment cost is reduced to a great extent, and the environment-friendly development concept is met.

Description

Treatment method of waste graphite crucible
Technical Field
The invention belongs to the technical field of radioactive waste treatment, and particularly relates to a treatment method of a waste graphite crucible.
Background
In the scientific research production process of the nuclear fuel element, a large number of waste graphite crucibles are produced, the waste graphite is mostly ashed at home and abroad, the volume reduction ratio of the waste graphite ashed can reach 160:1, the produced incineration ash is an inorganic inert substance, the safety is improved, and the disposal is facilitated.
At present, a clear treatment method for a low-level waste graphite crucible is not available, and an ashing treatment method is generally adopted for waste graphite, and because the number of waste graphite crucibles temporarily stored in the north of a middle core is large, the direct ashing treatment has large workload and high cost.
Disclosure of Invention
In order to overcome the defects, the invention aims to provide a treatment method of the waste graphite crucible, which can reduce the treatment cost by adopting mechanical separation-ashing and partial ashing to treat the waste graphite crucible and accords with the green development concept.
The technical scheme of the invention is as follows:
The method comprises the steps of firstly, performing source item investigation on a waste graphite crucible pollution layer to determine the pollution depth and the surface pollution degree;
Step two, mechanically cutting the inner surface layer of the polluted part of the waste graphite crucible before ashing; and ashing the polluted part, and preserving the non-polluted part.
And step three, cleaning the non-pollution part.
The ashing temperature T of the waste graphite crucible is 650 ℃ to less than or equal to T1 and less than or equal to 800 ℃, the temperature rising process is that the waste graphite crucible is kept for 1h after being heated to 200 ℃, the waste graphite crucible is kept warm for 1h after being kept warm, the temperature rising and the heat keeping time are totally called as reaction time, the reaction time T is 90h to less than or equal to T to less than or equal to 120h, and the ashing of the cut waste graphite crucible is completed.
In the ashing process of the waste graphite crucible, the molar ratio of the air inlet amount to the waste graphite crucible is 1:10-1:20.
The uranium content of the inner surface of the waste graphite crucible is 20% -70%, and other elements are C, O, Y.
And in the ashing process of the waste graphite crucible, the outer surface of the waste graphite crucible is contacted with the material boat.
The ashing temperature T of the waste graphite crucible is in the range of 650 ℃ to less than or equal to T1 and less than or equal to 800 ℃, the temperature rising process is that the waste graphite crucible is kept for 1h after being heated to 200 ℃, the waste graphite crucible is kept warm for 1h after being kept warm, the temperature rising and the heat keeping time are totally called as reaction time, the reaction time T is in the range of 72h to less than or equal to T to less than or equal to 90h, and a pollution layer is ashed.
In the ashing process of the waste graphite crucible, the molar ratio of the air inlet amount to the waste graphite crucible is=1:10-1:20.
The waste graphite crucible volume exceeds 200L.
The invention has the beneficial effects that:
The invention provides a certain technical support for the treatment of the waste graphite crucible pollution layer with fixed model and determined pollution degree; the mechanical separation-ashing and partial ashing are adopted to treat the waste graphite crucible, so that the burning cost and the personnel operation intensity can be effectively reduced, and meanwhile, the non-pollution waste graphite crucible is sold according to the price of high-purity waste graphite, the treatment cost is reduced to a great extent, and the environment-friendly development concept is met.
Detailed Description
The technical solutions of the embodiments of the present invention will be clearly and completely described below in conjunction with the embodiments of the present invention, and it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
Example 1:
firstly, performing source item investigation on a waste graphite crucible pollution layer to determine the pollution depth and the surface pollution degree;
Step two, mechanically cutting the inner surface layer of the polluted part of the waste graphite crucible before ashing; and ashing the polluted part, and preserving the non-polluted part.
The volume of the waste graphite crucible exceeds 200L, and the wall thickness is thicker, so that the waste graphite crucible is beneficial to cutting.
The ashing temperature T of the waste graphite crucible is 650 ℃ to 800 ℃ with the temperature rising process of T1 being more than or equal to 650 ℃: and (3) after the temperature is raised to 200 ℃, keeping the temperature for 1h at 100 ℃ and keeping the temperature for 90 h-120 h, wherein the heating and keeping time is the reaction time, and the range of the reaction time t is 90 h-120 h.
In the ashing process of the waste graphite crucible, the molar ratio of the air inlet amount to the waste graphite crucible is 1:10-1:20.
Example 2:
Firstly, carrying out source item investigation on a pollution layer in a waste graphite crucible to determine pollution elements and pollution degrees;
And step two, ashing the graphite crucible, and after ashing for a certain time, completely ashing the polluted part and preserving the non-polluted part.
And step three, cleaning the non-polluted part.
The volume of the waste graphite crucible exceeds 200L, and the wall thickness is thicker.
The uranium content of the inner surface of the waste graphite crucible is 20% -70%, and other elements are C, O, Y.
And in the ashing process of the waste graphite crucible, the outer surface of the waste graphite crucible is contacted with the material boat.
The ashing temperature T of the waste graphite crucible is 650 ℃ to 800 ℃ with the temperature rising process of T1 being more than or equal to 650 ℃: and (3) after the temperature is raised to 200 ℃, keeping the temperature for 1h at 100 ℃ each time, wherein the heating and the heat-keeping time are collectively called reaction time, the reaction time t is more than or equal to 72h and less than or equal to 90h, and the pollution layer is ashed.
In the ashing process of the waste graphite crucible, the molar ratio of the air inlet amount to the waste graphite crucible is=1:10-1:20.
Example 3: mechanical separation-ashing
Step one, taking a waste graphite crucible with an outer diameter of 500mm, an inner diameter of 400mm, a height of 620mm and a wall thickness of 50mm for source item investigation. The surface activity of the surface layer of the waste graphite crucible cleaned by the brush is less than 1Bq/cm 2, and when the waste graphite crucible is processed to the depth of 10mm, the surface pollution level is less than 0.08Bq/cm 2, so that the exemption level is achieved.
And step two, taking a complete graphite crucible, removing the surface oxide layer, performing preliminary crushing, and selecting a graphite block with larger crushed area to cut off the inner surface by 10mm.
And thirdly, uniformly loading the cut-off part into 2 material boats after secondary crushing, wherein each boat is charged with 500g, the ashing temperature is 800 ℃, the reaction time is 90h, and the air inlet amount is 300L/h. The ashed contaminated portion accounts for about 20% of the total mass.
Example 4: partial ashing
Step one, taking a waste graphite crucible with an outer diameter of 500mm, an inner diameter of 400mm, a height of 620mm and a wall thickness of 50mm for source item investigation. The uranium content of the inner surface of the waste graphite crucible is 20% -70%, and other elements are C, O, Y.
Step two, waste whole graphite crucible is crushed after oxide layer is removed, the diameter after crushing is about 100mm, the weight is 400-500 g, and the outer surface is contacted with a material boat in the ashing process of the graphite crucible. The ashing temperature was 800 ℃, the reaction temperature was 72 hours, and the air introduction amount was 300L.
Thirdly, the surface of the ashed waste graphite crucible block is honeycomb briquette, dust and particles in the graphite block are knocked and cleaned, and dust and particles attached to the surface of the ashed graphite block are collected by a brush. The ashed contaminated portion accounts for about 72% of the total mass.
The disclosed embodiments of the invention relate to methods related to the disclosed embodiments, other methods can refer to common designs, and the same embodiment and different embodiments of the invention can be combined with each other under the condition of no conflict;
The foregoing description of the preferred embodiments of the invention is not intended to limit the invention to the precise form disclosed, and any such modifications, equivalents, and alternatives falling within the spirit and principles of the invention are intended to be included within the scope of the invention.

Claims (7)

1. A method for processing waste graphite crucible is characterized in that: firstly, performing source item investigation on a waste graphite crucible pollution layer to determine the pollution depth and the surface pollution degree;
Step two, mechanically cutting the inner surface layer of the polluted part of the waste graphite crucible before ashing; ashing the polluted part, and storing the non-polluted part;
The method also comprises a step three of cleaning the non-pollution part;
the ashing temperature T of the waste graphite crucible is 650 ℃ to less than or equal to T1 and less than or equal to 800 ℃, the temperature rising process is that the waste graphite crucible is kept for 1h after being heated to 200 ℃, the waste graphite crucible is kept warm for 1h after being kept warm, the temperature rising and the heat keeping time are totally called as reaction time, the reaction time T is 90h to less than or equal to T to less than or equal to 120h, and the ashing of the cut waste graphite crucible is completed.
2. A method of treating a waste graphite crucible as set forth in claim 1, wherein: in the ashing process of the waste graphite crucible, the molar ratio of the air inlet amount to the waste graphite crucible is 1:10-1:20.
3. A method of treating a waste graphite crucible as set forth in claim 2, wherein: the uranium content of the inner surface of the waste graphite crucible is 20% -70%, and other elements are C, O, Y.
4. A method of treating a waste graphite crucible as set forth in claim 1, wherein: and in the ashing process of the waste graphite crucible, the outer surface of the waste graphite crucible is contacted with the material boat.
5. A method of treating a waste graphite crucible as set forth in claim 4, wherein: the ashing temperature T of the waste graphite crucible is in the range of 650 ℃ to less than or equal to T1 and less than or equal to 800 ℃, the temperature rising process is that the waste graphite crucible is kept for 1h after being heated to 200 ℃, the waste graphite crucible is kept warm for 1h after being kept warm, the temperature rising and the heat keeping time are totally called as reaction time, the reaction time T is in the range of 72h to less than or equal to T to less than or equal to 90h, and a pollution layer is ashed.
6. A method of treating a waste graphite crucible as set forth in claim 5, wherein: in the ashing process of the waste graphite crucible, the molar ratio of the air inlet amount to the waste graphite crucible is=1:10-1:20.
7. A method of treating a waste graphite crucible as claimed in any one of claims 1 to 6, wherein: the waste graphite crucible volume exceeds 200L.
CN202011310352.9A 2020-11-20 2020-11-20 Treatment method of waste graphite crucible Active CN112700902B (en)

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Citations (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2000056091A (en) * 1998-08-06 2000-02-25 Central Res Inst Of Electric Power Ind Volume reducing method for solid waste containing radioactive material including high-melting point and strong-activity metal
JP2001033587A (en) * 1999-07-23 2001-02-09 Ngk Insulators Ltd Treating method and device of radioactive graphite
JP2005114620A (en) * 2003-10-09 2005-04-28 Japan Nuclear Cycle Development Inst States Of Projects Decontamination method for ferrous metal contaminated with radioactive material
RU2435241C1 (en) * 2010-05-24 2011-11-27 Открытое акционерное общество "Свердловский научно-исследовательский институт химического машиностроения" (ОАО "СвердНИИхиммаш") Treatment method of radioactive contaminated metal and graphite wastes of uranium-graphite nuclear reactors
CN103466677A (en) * 2013-08-30 2013-12-25 北京科技大学 Method for removing arsenic and lead from limestone flour
CN103811091A (en) * 2012-11-08 2014-05-21 中国辐射防护研究院 High-level uranium pollution carbon steel or stainless steel smelting decontamination process
CN105883780A (en) * 2015-12-15 2016-08-24 中南大学 Method for preparing high-purity flake graphite
CN106098131A (en) * 2016-07-17 2016-11-09 邢桂生 A kind of nuke rubbish packing device
CN106531277A (en) * 2016-12-26 2017-03-22 西南科技大学 Processing method of radioactive graphite
CN108320830A (en) * 2017-12-28 2018-07-24 中核四0四有限公司 In one kind, low put metal waste hot spot stripping means
CN109961868A (en) * 2019-03-21 2019-07-02 西南科技大学 A kind of radioactive pollution graphite burning process
CN111470503A (en) * 2020-03-24 2020-07-31 山东锐轩新材料有限公司 Recycling method of garbage power generation fly ash chelate

Patent Citations (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2000056091A (en) * 1998-08-06 2000-02-25 Central Res Inst Of Electric Power Ind Volume reducing method for solid waste containing radioactive material including high-melting point and strong-activity metal
JP2001033587A (en) * 1999-07-23 2001-02-09 Ngk Insulators Ltd Treating method and device of radioactive graphite
JP2005114620A (en) * 2003-10-09 2005-04-28 Japan Nuclear Cycle Development Inst States Of Projects Decontamination method for ferrous metal contaminated with radioactive material
RU2435241C1 (en) * 2010-05-24 2011-11-27 Открытое акционерное общество "Свердловский научно-исследовательский институт химического машиностроения" (ОАО "СвердНИИхиммаш") Treatment method of radioactive contaminated metal and graphite wastes of uranium-graphite nuclear reactors
CN103811091A (en) * 2012-11-08 2014-05-21 中国辐射防护研究院 High-level uranium pollution carbon steel or stainless steel smelting decontamination process
CN103466677A (en) * 2013-08-30 2013-12-25 北京科技大学 Method for removing arsenic and lead from limestone flour
CN105883780A (en) * 2015-12-15 2016-08-24 中南大学 Method for preparing high-purity flake graphite
CN106098131A (en) * 2016-07-17 2016-11-09 邢桂生 A kind of nuke rubbish packing device
CN106531277A (en) * 2016-12-26 2017-03-22 西南科技大学 Processing method of radioactive graphite
CN108320830A (en) * 2017-12-28 2018-07-24 中核四0四有限公司 In one kind, low put metal waste hot spot stripping means
CN109961868A (en) * 2019-03-21 2019-07-02 西南科技大学 A kind of radioactive pollution graphite burning process
CN111470503A (en) * 2020-03-24 2020-07-31 山东锐轩新材料有限公司 Recycling method of garbage power generation fly ash chelate

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
坩埚灰化-ICP-AES法测定管输原油中金属元素含量;索金玲;吴珊;张金龙;徐颖洁;;石油炼制与化工;20130412(第04期);第100-104页 *

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