CN111560196A - Strippable film solutions for radionuclide decontamination, methods of making and using - Google Patents
Strippable film solutions for radionuclide decontamination, methods of making and using Download PDFInfo
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- CN111560196A CN111560196A CN202010425238.4A CN202010425238A CN111560196A CN 111560196 A CN111560196 A CN 111560196A CN 202010425238 A CN202010425238 A CN 202010425238A CN 111560196 A CN111560196 A CN 111560196A
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- decontamination
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- C—CHEMISTRY; METALLURGY
- C09—DYES; PAINTS; POLISHES; NATURAL RESINS; ADHESIVES; COMPOSITIONS NOT OTHERWISE PROVIDED FOR; APPLICATIONS OF MATERIALS NOT OTHERWISE PROVIDED FOR
- C09D—COATING COMPOSITIONS, e.g. PAINTS, VARNISHES OR LACQUERS; FILLING PASTES; CHEMICAL PAINT OR INK REMOVERS; INKS; CORRECTING FLUIDS; WOODSTAINS; PASTES OR SOLIDS FOR COLOURING OR PRINTING; USE OF MATERIALS THEREFOR
- C09D129/00—Coating compositions based on homopolymers or copolymers of compounds having one or more unsaturated aliphatic radicals, each having only one carbon-to-carbon double bond, and at least one being terminated by an alcohol, ether, aldehydo, ketonic, acetal, or ketal radical; Coating compositions based on hydrolysed polymers of esters of unsaturated alcohols with saturated carboxylic acids; Coating compositions based on derivatives of such polymers
- C09D129/02—Homopolymers or copolymers of unsaturated alcohols
- C09D129/04—Polyvinyl alcohol; Partially hydrolysed homopolymers or copolymers of esters of unsaturated alcohols with saturated carboxylic acids
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- C—CHEMISTRY; METALLURGY
- C09—DYES; PAINTS; POLISHES; NATURAL RESINS; ADHESIVES; COMPOSITIONS NOT OTHERWISE PROVIDED FOR; APPLICATIONS OF MATERIALS NOT OTHERWISE PROVIDED FOR
- C09D—COATING COMPOSITIONS, e.g. PAINTS, VARNISHES OR LACQUERS; FILLING PASTES; CHEMICAL PAINT OR INK REMOVERS; INKS; CORRECTING FLUIDS; WOODSTAINS; PASTES OR SOLIDS FOR COLOURING OR PRINTING; USE OF MATERIALS THEREFOR
- C09D171/00—Coating compositions based on polyethers obtained by reactions forming an ether link in the main chain; Coating compositions based on derivatives of such polymers
- C09D171/02—Polyalkylene oxides
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- C—CHEMISTRY; METALLURGY
- C09—DYES; PAINTS; POLISHES; NATURAL RESINS; ADHESIVES; COMPOSITIONS NOT OTHERWISE PROVIDED FOR; APPLICATIONS OF MATERIALS NOT OTHERWISE PROVIDED FOR
- C09D—COATING COMPOSITIONS, e.g. PAINTS, VARNISHES OR LACQUERS; FILLING PASTES; CHEMICAL PAINT OR INK REMOVERS; INKS; CORRECTING FLUIDS; WOODSTAINS; PASTES OR SOLIDS FOR COLOURING OR PRINTING; USE OF MATERIALS THEREFOR
- C09D5/00—Coating compositions, e.g. paints, varnishes or lacquers, characterised by their physical nature or the effects produced; Filling pastes
- C09D5/20—Coating compositions, e.g. paints, varnishes or lacquers, characterised by their physical nature or the effects produced; Filling pastes for coatings strippable as coherent films, e.g. temporary coatings strippable as coherent films
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- C—CHEMISTRY; METALLURGY
- C09—DYES; PAINTS; POLISHES; NATURAL RESINS; ADHESIVES; COMPOSITIONS NOT OTHERWISE PROVIDED FOR; APPLICATIONS OF MATERIALS NOT OTHERWISE PROVIDED FOR
- C09D—COATING COMPOSITIONS, e.g. PAINTS, VARNISHES OR LACQUERS; FILLING PASTES; CHEMICAL PAINT OR INK REMOVERS; INKS; CORRECTING FLUIDS; WOODSTAINS; PASTES OR SOLIDS FOR COLOURING OR PRINTING; USE OF MATERIALS THEREFOR
- C09D7/00—Features of coating compositions, not provided for in group C09D5/00; Processes for incorporating ingredients in coating compositions
- C09D7/40—Additives
- C09D7/60—Additives non-macromolecular
- C09D7/61—Additives non-macromolecular inorganic
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P20/00—Technologies relating to chemical industry
- Y02P20/50—Improvements relating to the production of bulk chemicals
- Y02P20/54—Improvements relating to the production of bulk chemicals using solvents, e.g. supercritical solvents or ionic liquids
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Abstract
The invention discloses a strippable film solution for radionuclide decontamination, and a preparation method and a use method thereof, wherein the strippable film solution is prepared from the following raw materials: 3.5-14.93 wt% of polyvinyl alcohol, 1-5 wt% of polyethylene glycol, 0.005-0.3 wt% of graphene oxide, 0.5-3mol/L of acid agent, 15-30 wt% of complexing agent and the balance of deionized water. Compared with the conventional polyvinyl alcohol film for decontamination reported in the prior literature, the novel strippable film has higher mechanical property. The test shows that the tensile strength of the peelable film on the horizontal surface is 23.6-62.1 MPa, and the tensile strength of the peelable film on the inclined surface and the peelable film on the vertical surface is 19.1-52.3 MPa. Meanwhile, the strippable film has a high decontamination coefficient, and the decontamination efficiency of common radioactive nuclides such as uranium, plutonium, strontium, cesium and cobalt is not lower than 85%. Meanwhile, by introducing a supercritical water oxidation technology, the method realizes the recycling of the radionuclide wrapped in the strippable film after decontamination, improves the utilization efficiency of the nuclide, and further reduces the requirement of secondary waste treatment.
Description
Technical Field
The invention relates to a peelable film solution for radionuclide decontamination, methods of making and using.
Background
The world nuclear industry has gone through a development history of over seventy years, and in the long development process, numerous nuclear facilities are built in countries of the world. These include various types of reactors, such as nuclear power plants, research reactors, microreactors, special power reactors, and the like; the method also comprises production and scientific research facilities in various nuclear fuel circulating systems, and relates to various process links such as uranium mining and metallurgy, uranium conversion, uranium concentration, fuel and material manufacturing, spent fuel aftertreatment and the like. In the daily operation of these nuclear facilities, surface contamination of radionuclides inevitably occurs at the site of the nuclear facility, and in order to maintain the radiation environment and the safety of personnel inside the facility, it is necessary to perform daily monitoring of the surface contamination of the facility building and the equipment, and if contamination is found, immediately perform decontamination. Meanwhile, a large amount of nuclear facilities are finished running and enter the stage of sealing and decommissioning. The ultimate aim of nuclear facility decommissioning is to open or reuse the original site, and in the decommissioning process, the removal of radionuclide pollution existing in the existing nuclear facility buildings and equipment is also a key process.
The existing radioactive decontamination process includes a physical decontamination process and a chemical decontamination process, including peelable film decontamination, detergent decontamination, ultrasonic decontamination, peeling decontamination, wiping decontamination, electrochemical decontamination, laser decontamination, etc., which are used according to different decontamination conditions, and key indexes determining the decontamination process include: high decontamination factor, low secondary waste amount, easy secondary waste treatment and less manual operation.
The strippable film technology is widely applied to the decommissioning of foreign nuclear facilities in recent years, and the basic principle is that a layer of liquid is coated on the surface of an article to be decontaminated, the liquid forms a film with certain strength on the surface to be decontaminated after being dried, and then the film is lifted. On the whole, the method is an ideal decontamination process with high decontamination coefficient and less secondary waste, but the problems of insufficient mechanical strength of the film and the like still cause unexpected situations such as possible breakage and the like in the stripping process, and meanwhile, the radioactive nuclide in the strippable film is difficult to collect and utilize.
Disclosure of Invention
In view of the above-mentioned technical deficiencies, it is an object of the present invention to provide a novel peelable film having a high adsorption capacity; the strippable film has higher mechanical strength; meanwhile, the invention also designs a method for further processing the recycled polluted strippable film and collecting the radioactive nuclide in the strippable film.
In order to solve the technical problems, the invention adopts the following technical scheme:
the invention provides a novel strippable film solution which is prepared from the following raw materials: 3.5-14.93 wt% of polyvinyl alcohol, 1-5 wt% of polyethylene glycol, 0.005-0.3 wt% of graphene oxide, 0.5-3mol/L of acid agent, 15-30 wt% of complexing agent and the balance of deionized water.
The invention also provides a method for preparing a peelable film solution, according to 1: weighing graphene oxide powder and deionized water according to a mass ratio of 100, dispersing the graphene oxide powder in the deionized water, and ultrasonically stripping until a dark brown stable suspension is formed; preparing 5-15% PVA solution under the condition of water bath at 90 ℃, weighing 1 part of PVA solution, mixing with 0.005-0.43 part of dark brown stable graphene oxide suspension, adding 1-5 wt% of polyethylene glycol, 0-2 wt% of complexing agent and 0.5-3mol/L acid agent according to the mass and volume of the mixed solution, and uniformly mixing at room temperature.
The use method of the strippable film solution provided by the invention comprises the following steps: when the coating is used on the horizontal surface of buildings, equipment and workpieces, the coating comprises any one of spray forming, tape casting and manual coating forming.
Preferably, casting is adopted when the horizontal direction surface of buildings, equipment and workpieces is used.
The use method of the other strippable film solution provided by the invention comprises the following steps: when the coating is used on the inclined and vertical surfaces of buildings, equipment and workpieces, spray forming and manual coating forming are adopted.
Preferably, the spray forming is adopted when the inclined and vertical surfaces of buildings, equipment and workpieces are used.
The invention also provides a recovery and reprocessing process of the strippable film, and after the strippable solution is formed and constructed, the strippable solution is stripped from the decontamination surface by adopting a mechanical or manual stripping mode after being naturally dried for 8-72 h; and crushing the stripped strippable film in a closed glove box, mixing the stripped strippable film with water to form a recovered feed liquid, heating the recovered feed liquid, sending the heated feed liquid into a supercritical water oxidation treatment device for treatment, discharging waste gas generated after treatment through a gas filter, and performing ion adsorption and exchange on the liquid containing the radionuclide to complete the collection of the radionuclide.
The invention has the beneficial effects that: compared with the conventional polyvinyl alcohol film for decontamination reported in the prior literature, the strippable film has higher mechanical property. The test shows that the tensile strength of the peelable film on the horizontal surface is 23.6-62.1 MPa, and the tensile strength of the peelable film on the inclined surface and the peelable film on the vertical surface is 19.1-52.3 MPa. Meanwhile, the strippable film has a high decontamination coefficient, and the decontamination efficiency of common radioactive nuclides such as uranium, plutonium, strontium, cesium and cobalt is not lower than 85%. Meanwhile, by introducing a supercritical water oxidation technology, the method realizes the recycling of the radionuclide wrapped in the strippable film after decontamination, improves the utilization efficiency of the nuclide, and further reduces the requirement of secondary waste treatment.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to the drawings without creative efforts.
Fig. 1 is a schematic flow chart of a method for preparing a peelable film solution for radionuclide decontamination according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Fig. 1 is a schematic flow chart of a method for preparing a peelable film solution for radionuclide decontamination according to an embodiment of the present invention.
The present invention is described in further detail below by way of specific embodiments:
example 1
According to the following steps: weighing 4.3g of graphene oxide powder and 430ml of deionized water according to the mass ratio of 100, dispersing the graphene oxide powder in the deionized water, and carrying out ultrasonic stripping until a dark brown stable suspension is formed. Preparing 1L of 5% PVA solution under the condition of water bath at 90 ℃, mixing the 1L PVA solution with 430ml of dark brown stable graphene oxide suspension, adding 28.6g of polyethylene glycol and 291.72g of phosphoric acid, and uniformly mixing at room temperature for later use.
Manually smearing the prepared strippable film solution on the surface of a uranium-polluted stainless steel workpiece for molding, and stripping from the decontamination surface by adopting a manual stripping mode after the uranium-polluted stainless steel workpiece is naturally dried for 72 hours, wherein the measured tensile strength is 19.1 MPa.
Example 2
According to the following steps: weighing 50mg of graphene oxide powder and 5ml of deionized water according to the mass ratio of 100 respectively, dispersing the graphene oxide in the deionized water, and carrying out ultrasonic stripping until a dark brown stable suspension is formed. Preparing 1L of PVA solution with the concentration of 15% under the condition of water bath at 90 ℃, mixing the 1L of PVA solution with 5ml of dark brown stable graphene oxide suspension, adding 10g of polyethylene glycol and 20g of EDTA, and uniformly mixing at room temperature for later use.
Uniformly spraying the prepared strippable film solution on the plutonium-polluted building cement wall by using a high-pressure spray gun, and stripping from the decontamination surface by adopting a mechanical stripping mode after the building cement wall is naturally dried for 8 hours; and the stripped strippable film is crushed in a closed glove box and then is mixed with water to form a recovery feed liquid, the recovery feed liquid is heated and then is sent to a supercritical water oxidation treatment device for treatment, waste gas generated after treatment is discharged through a gas filter, and the plutonium-containing waste liquid is subjected to ion adsorption exchange to complete the collection of radionuclides.
Example 3
According to the following steps: weighing 1g of graphene oxide powder and 100ml of deionized water according to the mass ratio of 100, dispersing the graphene oxide in the deionized water, and carrying out ultrasonic stripping until a dark brown stable suspension is formed. Preparing 10% PVA solution 1L under the condition of water bath at 90 ℃, mixing the 1LPVA solution with 100ml of dark brown stable graphene oxide suspension, adding 55g of polyethylene glycol, 10g of EDTA and 500g of concentrated hydrochloric acid, and uniformly mixing at room temperature for later use.
Casting the prepared strippable film solution on the horizontal surface of equipment polluted by cobalt for molding, and stripping from the surface to be decontaminated by adopting a mechanical stripping mode after the strippable film solution is naturally dried for 24 hours; and crushing the stripped strippable film in a closed glove box, mixing the stripped strippable film with water to form a recovered feed liquid, heating the recovered feed liquid, sending the heated feed liquid into a supercritical water oxidation treatment device for treatment, discharging waste gas generated after treatment through a gas filter, and collecting radionuclides from cobalt-containing waste liquid through ion adsorption and exchange.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is also intended to include such modifications and variations.
Claims (7)
1. A peelable film solution for radionuclide decontamination, characterized by being prepared from the following raw materials: 3.5-14.93 wt% of polyvinyl alcohol, 1-5 wt% of polyethylene glycol, 0.005-0.3 wt% of graphene oxide, 0.5-3mol/L of acid agent, 15-30 wt% of complexing agent and the balance of deionized water.
2. The method of preparing a peelable film solution according to claim 1 wherein the ratio of 1: weighing graphene oxide powder and deionized water according to a mass ratio of 100, dispersing the graphene oxide powder in the deionized water, and ultrasonically stripping until a dark brown stable suspension is formed; preparing 5-15% PVA solution under the condition of water bath at 90 ℃, weighing 1 part of PVA solution, mixing with 0.005-0.43 part of dark brown stable graphene oxide suspension, adding 1-5 wt% of polyethylene glycol, 0-2 wt% of complexing agent and 0.5-3mol/L of acid agent according to the mass and volume of the mixed solution, and uniformly mixing at room temperature.
3. The method of using the peelable film solution according to claim 1, wherein the method of using the peelable film solution for horizontal surfaces of buildings, facilities, and workpieces comprises any one of spray forming, tape casting, and hand coating.
4. The method of using the peelable film solution according to claim 3, wherein casting is employed when the horizontal direction surface of a building, an apparatus, or a work is used.
5. The method of using the peelable film solution according to claim 1, wherein the peelable film solution is formed by spray molding or hand coating when used on inclined and vertical surfaces of buildings, facilities, and workpieces.
6. The method of using the peelable film solution according to claim 5 wherein spray forming is used for inclined and vertical surfaces of buildings, equipment, and workpieces.
7. The recovery and reprocessing process of the strippable film, characterized in that the strippable solution of claim 1 is stripped from the surface to be decontaminated by mechanical or manual stripping after it is naturally dried for 8-72 hours after being applied; and crushing the stripped strippable film in a closed glove box, mixing the stripped strippable film with water to form a recovered feed liquid, heating the recovered feed liquid, sending the heated feed liquid into a supercritical water oxidation treatment device for treatment, discharging waste gas generated after treatment through a gas filter, and performing ion adsorption and exchange on the liquid containing the radionuclide to complete the collection of the radionuclide.
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| Application Number | Priority Date | Filing Date | Title |
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| CN202010425238.4A CN111560196A (en) | 2020-05-19 | 2020-05-19 | Strippable film solutions for radionuclide decontamination, methods of making and using |
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| CN202010425238.4A CN111560196A (en) | 2020-05-19 | 2020-05-19 | Strippable film solutions for radionuclide decontamination, methods of making and using |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113480896A (en) * | 2021-08-27 | 2021-10-08 | 核工业北京化工冶金研究院 | Polyvinyl alcohol strippable membrane radioactive detergent and use method thereof |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113480896A (en) * | 2021-08-27 | 2021-10-08 | 核工业北京化工冶金研究院 | Polyvinyl alcohol strippable membrane radioactive detergent and use method thereof |
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