CN114367290A - Preparation and application method of radioactive decontamination strippable membrane thermosensitive degradation catalyst - Google Patents

Preparation and application method of radioactive decontamination strippable membrane thermosensitive degradation catalyst Download PDF

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Publication number
CN114367290A
CN114367290A CN202111634587.8A CN202111634587A CN114367290A CN 114367290 A CN114367290 A CN 114367290A CN 202111634587 A CN202111634587 A CN 202111634587A CN 114367290 A CN114367290 A CN 114367290A
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parts
radioactive decontamination
degradation
deionized water
decontamination
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CN202111634587.8A
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Chinese (zh)
Inventor
张宇
习海玲
罗学刚
李占国
张丽
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Southwest University of Science and Technology
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Southwest University of Science and Technology
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Priority to CN202111634587.8A priority Critical patent/CN114367290A/en
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    • BPERFORMING OPERATIONS; TRANSPORTING
    • B01PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01JCHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
    • B01J23/00Catalysts comprising metals or metal oxides or hydroxides, not provided for in group B01J21/00
    • B01J23/70Catalysts comprising metals or metal oxides or hydroxides, not provided for in group B01J21/00 of the iron group metals or copper
    • B01J23/76Catalysts comprising metals or metal oxides or hydroxides, not provided for in group B01J21/00 of the iron group metals or copper combined with metals, oxides or hydroxides provided for in groups B01J23/02 - B01J23/36
    • B01J23/84Catalysts comprising metals or metal oxides or hydroxides, not provided for in group B01J21/00 of the iron group metals or copper combined with metals, oxides or hydroxides provided for in groups B01J23/02 - B01J23/36 with arsenic, antimony, bismuth, vanadium, niobium, tantalum, polonium, chromium, molybdenum, tungsten, manganese, technetium or rhenium
    • B01J23/843Arsenic, antimony or bismuth
    • B01J23/8437Bismuth
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/301Processing by fixation in stable solid media
    • G21F9/307Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars

Abstract

The invention discloses a preparation and application method of a radioactive decontamination strippable membrane thermosensitive degradation catalyst, which comprises 40-50 parts by weight of Bi (NO)3)320-25 parts of Sr (NO)3)2Dissolving in deionized water; 15 to 20 portions of H2C2O4Dissolving in deionized water; stirring at 1000r/min in Bi (NO)3)3、Sr(NO3)2Dropwise adding H into the mixed solution2C2O4Stirring the solution for 10 hours, and then adjusting the pH value to 7 by using ammonia water; adding 20-25 parts of Fe2O3Stirring continuously, and washing precipitates obtained after reaction for 3 hours with distilled water for 5 times; drying in a drying oven at 80 ℃, crushing to 60 meshes, heating to 750 ℃ at a speed of 10 ℃/min in a muffle furnace, preserving heat for 720 min, and then annealing and cooling; washing with deionized water, oven drying at 40 deg.C, and pulverizing to 100 mesh. Before using, the product is in a range of 3%. E8 percent of the raw materials are added and uniformly stirred, and are peeled off after being used, and are naturally stockpiled for 20-30 days, and the degradation rate is more than or equal to 90 percent.

Description

Preparation and application method of radioactive decontamination strippable membrane thermosensitive degradation catalyst
Technical Field
The invention relates to a preparation method and application of a radioactive decontamination strippable membrane thermosensitive degradation catalyst, which is Bi (NO)3)3、Sr(NO3)2、Fe2O3、H2C2O4A compound formed by (oxalic acid) and application thereof, belonging to the technical field of radioactive three wastes treatment and disposal in the technical field of nuclear science.
Background
Since the 80 s in the 20 th century, along with the retirement of a large number of nuclear facilities and the treatment of radioactive wastes at home and abroad, the surface decontamination technology of strippable decontamination films is developed and formed. The strippable dirt film is used for decontamination, the decontaminating agent is sprayed or brushed on the surface of a nuclear facility matrix, loose pollutants or certain semi-solid pollutants on the surface of the matrix can be enriched on the film through adhesive force and cohesive force in the drying and film forming process of the decontaminating agent, a layer of film can be formed on the surface of the facility matrix after the film liquid is dried, and then the dirt film is stripped, so that the purposes of decontamination, sealing and fixing the pollutants are achieved. Compared with other decontamination methods, the strippable film does not generate waste liquid in the decontamination process, is simple and convenient to spray, is easy to strip and recover from the surface, has low cost and can be mechanically operated in a large area.
At present, the peelable decontamination film matrix material is mainly polyacrylic resin, polyethylene resin (such as polyvinyl alcohol and polyvinyl acetate), polyurethane, cellulose and the like. The large amount of wastes which are generated after use and are difficult to naturally decompose become new pollution sources and even cause serious secondary pollution. In practical application of the strippable dirty film surface decontamination technology, the dry film thickness of the strippable dirty film is at least 50 micrometers so as to ensure the strippability and the protective performance of the strippable dirty film, 35-50 t of strippable dirty film waste is generated in the surface decontamination process of 1 square kilometer in terms of 35-50 g of usage amount per square meter, and the strippable dirty film waste with various pollutants generated in the process brings huge threats and hazards to the peripheral public health and the natural environment. Although a plurality of efficient and rapid decontamination film volume reduction and weight reduction methods including physical, chemical, biological and other treatment methods are explored at home and abroad, the problems of high cost, serious secondary pollution and the like still exist.
At present, the mature degradation of synthesized macromolecules such as strippable fouling films is a photocatalytic degradation technology, and the mechanism is that electrons on a valence band of a photocatalyst are larger than a forbidden band thereofWhen the light irradiation with the width energy is carried out, the light is excited to jump to the conduction band, corresponding holes are left on the valence band, the generated electron-hole pair generally has the service life of picosecond level, the photoproduction electron and the photoproduction hole pair can transfer charges to substances from solution or gas phase adsorbed on the surface of the photodegradation catalyst through forbidden bands, negatively charged electrons and positively charged holes are generated, and oxygen adsorbed on the surface of the photodegradation catalyst is trapped by electrons to form O2−While the holes will adsorb on the catalyst surface to make OH-And H2O is oxidized to HO, O2-HO, oxidative stripping of the fouling film, etc., to break the C-C bond of the synthetic polymer, ultimately achieving degradation. However, in the case where sunlight cannot be directly irradiated, such as a large amount of synthetic polymer wastes in refuse landfills, compost fields, mulching film soil-burying parts, etc., the photocatalytic degradation technology is greatly limited. How to screen different types of novel degradation catalysts, develop products with high utilization rate of catalytic factors such as ambient light, temperature, water, gas, biology and the like, meet the use requirements, have long lasting effect, are controllable and have low price, are a development direction of degrading synthetic macromolecules such as strippable fouling films and the like in future, and the research and development technical achievements of the products have important application prospects and significance for sustainable development of nuclear power, national defense military industry and nuclear science technology.
Disclosure of Invention
The invention aims to provide a preparation and application method of a radioactive decontamination strippable membrane thermosensitive degradation catalyst, which provides a technical method for treating and disposing surface decontamination by radioactive three wastes in the technical field of nuclear science, wherein the preparation method is simple, the cost is low, the application is convenient, the catalyst is suitable for degradation treatment of various radioactive decontamination strippable membranes, and the technical method can achieve rapid volume reduction, weight reduction and minimum treatment after use.
The technical scheme of the invention is as follows:
a preparation method of a radioactive decontamination peelable film heat-sensitive degradation catalyst is characterized by sequentially comprising the following steps:
A. preparing raw materials: weighing the following components in parts by weight: 340-50 parts of Bi (NO 3); 220-25 parts of Sr (NO 3); 320-25 parts of Fe 2O; 415-20 parts of H2C2O for later use;
B. dissolving Bi (NO3)3 and Sr (NO3)2 into 2000 parts of deionized water;
C. dissolving H2C2O4 into 500 parts of deionized water;
D. dropwise adding H2C2O4 solution into the mixed solution of Bi (NO3)3 and Sr (NO3)2 under the stirring condition of 1000r/min, stirring for 10H, and adjusting the pH of the solution to 7 by using ammonia water;
E. adding Fe2O3, stirring continuously, reacting for 3h to obtain a red-gray precipitate, and washing with distilled water for 5 times;
F. drying the cleaned precipitate in an electrothermal blowing drying oven at 80 ℃, crushing to 60 meshes, heating to 750 ℃ at a speed of 10 ℃/min in a muffle furnace, preserving heat for 720 min, and then annealing and cooling;
G. washing with deionized water, drying in a 40 ℃ oven, and crushing to 100 meshes to obtain the radioactive decontamination strippable membrane degradation catalyst.
The application method of the radioactive decontamination peelable film heat-sensitive degradation catalyst according to claim 1 comprises the steps of adding 3-5% of the radioactive decontamination peelable film by weight percent before use, uniformly stirring, peeling after use, naturally storing for 20-30 days, and enabling the degradation rate to be more than or equal to 90%.
The application method of the radioactive decontamination peelable film heat-sensitive degradation catalyst according to claim 1 is that the radioactive decontamination peelable film is added and uniformly mixed according to the weight percentage of 6-8% after being peeled off, and is naturally stored for 20-30 days, and the degradation rate is more than or equal to 90%.
Synthetic high molecular polymers such as radioactive decontamination strippable films provide safety and technical guarantee for the sustainable development of nuclear power, national defense and military industry and nuclear science technology, and simultaneously generate great potential hidden dangers, and a large amount of radioactive decontamination strippable film wastes which are difficult to naturally decompose become new pollution sources and even cause serious secondary pollution. Under the background of various problems existing in photodegradation, biodegradation, photo/biodegradation and thermal-oxidative degradation polymer technologies, how to develop a strippable fouling film waste degradation process with low cost, capability of meeting use requirements, rapid volume reduction and weight reduction, minimized pollution and even zero harm becomes one of the key technologies for surface decontamination in the future radioactive three wastes treatment and disposal. According to the invention, the negative temperature coefficient thermal-sensitive catalytic effect is utilized, namely, in a normal temperature environment of 20-40 ℃, the thermal-sensitive degradation catalyst can effectively catalyze and generate free radicals for strippable membrane degradation, and the polymerized polymer chain is cut off to realize thermal-catalytic controllable degradation. The invention has the innovation that the thermosensitive catalyst has low consumption, low cost and easy processing, meets the use requirement, and the used radioactive decontamination strippable membrane waste can be quickly subjected to volume reduction, weight reduction and degradation in a normal-temperature hot environment within a set time range and realizes the minimum treatment and disposal of the radioactive waste. The thermosensitive degradation catalyst prepared by the invention can also be used in the degradation treatment of volume reduction and weight reduction of synthetic high polymer material wastes such as polyethylene, polypropylene, polystyrene, polyurethane, polyamide and the like.
Detailed Description
The present invention will be described in further detail with reference to examples.
Example 1: taking Bi (NO) according to the weight portion3)345 portions of Sr (NO)3)220 parts of Fe2O325 portions of H2C2O415 parts of (1); in the first step, Bi (NO)3)3、Sr(NO3)2Dissolving in 2000 parts of deionized water; the second step is to mix H2C2O4Dissolving into 500 parts of deionized water; the third step is to stir the mixture at 1000r/min in Bi (NO)3)3、Sr(NO3)2Dropwise adding H into the mixed solution2C2O4Stirring the solution for 10 hours, and then adjusting the pH value of the solution to 7 by using ammonia water; fourth, adding Fe2O3Stirring continuously, reacting for 3h to obtain a red-gray precipitate, and washing with distilled water for 5 times; fifthly, putting the cleaned precipitate into an electric heating blast drying oven at 80 ℃, drying, crushing to 60 meshes, heating to 750 ℃ at a speed of 10 ℃/min in a muffle furnace, preserving heat for 720 min, and then annealing and cooling; and sixthly, cleaning with deionized water, drying in a 40 ℃ oven, and crushing to 100 meshes to obtain the radioactive decontamination strippable membrane thermosensitive degradation catalyst.
The radioactive decontamination strippable film is added according to the weight percentage of 3 percent before use and is evenly stirred, and is stripped after use and naturally stockpiled for 30 days with the degradation rate of 91 percent. After the radioactive decontamination strippable film is used and stripped, the radioactive decontamination strippable film is added according to the weight percentage of 8 percent and is uniformly mixed, and the radioactive decontamination strippable film is naturally stockpiled for 20 days with the degradation rate of 96 percent.
Example 2: taking Bi (NO) according to the weight portion3)340 portions of Sr (NO)3)223 parts of Fe2O322 portions of H2C2O420 parts of (1); in the first step, Bi (NO)3)3、Sr(NO3)2Dissolving in 2000 parts of deionized water; the second step is to mix H2C2O4Dissolving into 500 parts of deionized water; the third step is to stir the mixture at 1000r/min in Bi (NO)3)3、Sr(NO3)2Dropwise adding H into the mixed solution2C2O4Stirring the solution for 10 hours, and then adjusting the pH value of the solution to 7 by using ammonia water; fourth, adding Fe2O3Stirring continuously, reacting for 3h to obtain a red-gray precipitate, and washing with distilled water for 5 times; fifthly, putting the cleaned precipitate into an electric heating blast drying oven at 80 ℃, drying, crushing to 60 meshes, heating to 750 ℃ at a speed of 10 ℃/min in a muffle furnace, preserving heat for 720 min, and then annealing and cooling; and sixthly, cleaning with deionized water, drying in a 40 ℃ oven, and crushing to 100 meshes to obtain the radioactive decontamination strippable membrane thermosensitive degradation catalyst.
The radioactive decontamination strippable film is added in 4 percent by weight before use and is uniformly stirred, and is stripped after use and naturally stockpiled for 27 days, wherein the degradation rate is 92 percent. The radioactive decontamination strippable film is added and uniformly mixed according to the weight percentage of 7 percent after being used and stripped, and is naturally stockpiled for 26 days, and the degradation rate is 94 percent.
Example 3: taking Bi (NO) according to the weight portion3)350 portions of Sr (NO)3)225 parts of Fe2O320 portions of H2C2O418 parts of a mixture; in the first step, Bi (NO)3)3、Sr(NO3)2Dissolving in 2000 parts of deionized water; the second step is to mix H2C2O4Dissolving into 500 parts of deionized water; the third step is to stir the mixture at 1000r/min in Bi (NO)3)3、Sr(NO3)2Dropwise adding H into the mixed solution2C2O4Stirring the solution for 10 hours, and then adjusting the pH value of the solution to 7 by using ammonia water; fourth, adding Fe2O3Stirring continuously, reacting for 3h to obtain a red-gray precipitate, and washing with distilled water for 5 times; fifthly, putting the cleaned precipitate into an electric heating blast drying oven at 80 ℃, drying, crushing to 60 meshes, heating to 750 ℃ at a speed of 10 ℃/min in a muffle furnace, preserving heat for 720 min, and then annealing and cooling; and sixthly, cleaning with deionized water, drying in a 40 ℃ oven, and crushing to 100 meshes to obtain the radioactive decontamination strippable membrane thermosensitive degradation catalyst.
The radioactive decontamination strippable film is added according to the weight percentage of 5 percent before use and is evenly stirred, and is stripped after use and naturally stockpiled for 20 days, and the degradation rate is 92 percent. After the radioactive decontamination strippable film is used and stripped, the radioactive decontamination strippable film is added according to the weight percentage of 6 percent and is uniformly mixed, and the radioactive decontamination strippable film is naturally stockpiled for 30 days with the degradation rate of 94 percent.
The above description is only for the preferred embodiment of the present invention, but the scope of the present invention is not limited thereto, and any changes or substitutions that can be easily conceived by those skilled in the art within the technical scope of the present invention are included in the scope of the present invention.

Claims (3)

1. A preparation method of a radioactive decontamination peelable film heat-sensitive degradation catalyst is characterized by sequentially comprising the following steps:
A. preparing raw materials: weighing the following components in parts by weight: bi (NO)3)340-50 parts; sr (NO)3)220-25 parts; fe2O320-25 parts; h2C2O415-20 parts for later use;
B. adding Bi (NO)3)3、Sr(NO3)2Dissolving in 2000 parts of deionized water;
C. h is to be2C2O4Dissolving into 500 parts of deionized water;
D. stirring at 1000r/min in Bi (NO)3)3、Sr(NO3)2Dropwise adding H into the mixed solution2C2O4Stirring the solutionStirring for 10 h, and adjusting the pH value of the solution to 7 by using ammonia water;
E. adding Fe2O3Stirring continuously, reacting for 3h to obtain a red-gray precipitate, and washing with distilled water for 5 times;
F. drying the cleaned precipitate in an electrothermal blowing drying oven at 80 ℃, crushing to 60 meshes, heating to 750 ℃ at a speed of 10 ℃/min in a muffle furnace, preserving heat for 720 min, and then annealing and cooling;
G. washing with deionized water, drying in a 40 ℃ oven, and crushing to 100 meshes to obtain the radioactive decontamination strippable membrane degradation catalyst.
2. The application method of the radioactive decontamination peelable film heat-sensitive degradation catalyst is characterized in that the radioactive decontamination peelable film is added according to the weight percentage of 3-5% before use and is uniformly stirred, and is peeled off after use and naturally stored for 20-30 days, wherein the degradation rate is more than or equal to 90%.
3. The application method of the radioactive decontamination peelable film heat-sensitive degradation catalyst is characterized in that the radioactive decontamination peelable film is added and uniformly mixed according to the weight percentage of 6-8% after being peeled off, and is naturally stored for 20-30 days, and the degradation rate is more than or equal to 90%.
CN202111634587.8A 2021-12-29 2021-12-29 Preparation and application method of radioactive decontamination strippable membrane thermosensitive degradation catalyst Pending CN114367290A (en)

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