2524results about "Radioactive decontamination" patented technology

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a sealing device and curing equipment. According to the sealing device and the curing equipment provided by the embodiment of the invention, the blocking assembly and the sealing assembly jointly block the first opening formed by the material treatment device, so that the material treatment device is subjected to double sealing, and the internal material treatment environment is more stable; the locking assembly is driven to move in the circumferential direction so as to fix the plugging assembly to the sealing assembly, meanwhile, the locking assembly is arranged to be axially static so as to further reinforce fixation between the plugging assembly and the sealing assembly, and the material containing device can be more stable in the material treatment device; and good sealing performance and stability in the material treatment process are ensured.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a material containing device and curing equipment. The first containing piece and the second containing piece of the material containing device are arranged to be in a detachable and separable form, so that powdery radioactive materials cannot escape from a seam, and meanwhile, after the powdery materials are pressed into solid materials, the first containing piece and the second containing piece can be separated; the solid materials contained in the first containing part can be independently transferred, the material containing device is prevented from being integrally transferred when the solid materials are transferred, and the transferring efficiency of the solid materials is improved. According to the curing equipment, the material containing device is adopted as a material conveying carrier, materials in different stages and states in the curing process can be contained, and leakage of the materials is prevented; meanwhile, in the whole curing process, form transformation of the materials can be achieved without replacing the containing device, the operation process is simplified, material spill caused by replacing the containing device is avoided, and therefore the curing efficiency is improved.

The invention provides an integrated containment pressure suppression, filtration and discharge system. The integrated containment pressure suppression, filtration and discharge system comprises a containment, a discharge valve, a discharge pipeline, a spray pipe, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, a baffle plate steam-water separator, an expansion tank, a rupture disk structure, a combined metal fiber filter layer, a radioactivity monitor, a first stop valve and a second stop valve. The two-stage pressure suppression water tank is arranged, the high removal efficiency of airborne radioactive substances is achieved through two-stage bubbling water washing, then the combined metal fiber filter is arranged by means of an existing cabin, and the requirements for rapid pressure reduction and radioactive substance removal of the containment under the LOCA accident working condition can be met; meanwhile, the problem that the containment filtering and discharging system of the existing nuclear power station occupies too many resources is solved, and the economical efficiency is high.

The invention provides a device and method for removing aerosol based on a charged spraying coupling pool washing mechanism, and belongs to the field of nuclear auxiliary systems. The problem that radioactive aerosol particles generated when a radioactive contamination structure in a reactor is cut underwater can be released into the external environment is solved. Wherein the underwater laser cutting assembly is used for cutting a to-be-cut piece; the auxiliary gas chamber is communicated with the laser cutting nozzle; the aerosol charging assembly can enable aerosol particles generated by underwater laser cutting to carry negative charges; the baffle can gather the aerosol particles and guide the aerosol particles to the aerosol charging assembly; the liquid drop charged spraying assembly can spray liquid drops carrying positive charges, the liquid drops carrying positive charges and aerosol particles carrying negative charges can attract each other and fall to the liquid level, and the Venturi washing assembly can extract gas above the liquid level and spray the gas below the liquid level. The device can efficiently remove radioactive aerosol particles generated by cutting and disassembling radioactive contaminated components in a nuclear power plant, and radioactive contamination to the environment is prevented.

The present invention is directed towards methods for isolating molybdenum compounds from a mixture of fission products. The mixture of fission products may be extracted from a molten salt reactor system. Utilizing a phase transfer agent, the molybdenum compounds may be extracted from an aqueous solution into an organic solution, thereby isolating the molybdenum compound from the mixture of fission products. Molybdate may then be isolated from the resulting organic solution and provided to a generator to facilitate transformation into technitum-99m.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to material treatment equipment and curing equipment. According to the material treatment equipment provided by the embodiment of the invention, the powdery material in the material accommodating device is converted into a partially molten state through the material treatment device, and the partially molten material is converted into the solid material through the pressurizing device, so that the powdery material can undergo conversion of different states in the material accommodating device; therefore, powdery materials are converted into solid materials convenient to transfer and process, the operation of replacing a container is omitted, and material processing procedures are saved. According to the curing equipment provided by the embodiment of the invention, the sealing device is used for sealing the material treatment equipment, so that the state transition process of the powdery material has better sealing performance and stability, and the stable quality of the produced solid material is ensured.

The phosphazene covalent organic framework (COF) is a material with high efficiency to improve the removal of iodine from nuclear waste. The COF can be obtained by a solvothermal reaction of hexa(4-formyl-phenoxy)cyclotriphosphazene and 1,3,6,8-tetra(aminophenyl)pyrene. The resulting three-dimensional phosphazene COF has iodine uptakes as high as 9.4 g g−1 due to its 3D framework with higher specific surface areas and interconnected channels.

The invention relates to the technical field of radioactive pollutant removal, in particular to a movable surface Po-210 pollution treatment device and a testing method thereof.The pollution treatment device comprises a movable vehicle body capable of automatically moving; the positioning assembly is arranged on the mobile vehicle body and can automatically identify and identify a pollution object with the surface Po-210 pollution needing to be treated; the multi-shaft mechanical arm is mounted on the movable vehicle body; the decontamination assembly is installed at the moving end of the multi-axis mechanical arm, and the decontamination assembly comprises a film forming raw material spray head, a film uncovering scraper knife, a dirty film clamp and a coating film raw material spray head; a spraying raw material supply system; wherein the film forming raw material spray head and the coating film raw material spray head are connected with a spraying raw material supply system, the film uncovering scraper knife can be driven by the multi-axis mechanical arm to shovel up a dirty film formed by film forming raw materials on a polluted object, and the dirty film clamp can clamp the dirty film shoveled up by the film uncovering scraper knife. The testing method is used for testing the pollution treatment device.

The invention relates to the technical field of high-level liquid waste evaporation in nucleation post-treatment and nucleation glass curing, in particular to a liquid waste evaporation end point automatic judgment method and a liquid waste evaporation control method and device. The method comprises the following steps: acquiring waste liquid parameters of an evaporation system before evaporation and target parameters of waste liquid in a kettle type evaporator after evaporation; determining the target liquid level in the stock solution tank after evaporation according to the mass of the standard substance before evaporation calculated according to the waste liquid parameters, the target parameters of the waste liquid and the mass conservation of the standard substance before and after evaporation; according to the method, the mass of the standard substance of the waste liquid in the evaporation process is analyzed, and the evaporation end point is determined through mass conservation of the standard substance before and after evaporation, so that the evaporation end point can be automatically determined by analyzing the parameters of the waste liquid in the evaporation system, and the efficiency of the evaporation system is improved. Meanwhile, the evaporation end point is determined based on mass analysis and calculation of the target substance, so that the determination of the evaporation end point is more accurate.

The invention provides a containment suppression, filtration and discharge system for a floating nuclear power platform. Comprising a containment, a first discharge valve, a first discharge pipeline, a first spray pipe, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, an expansion cabin, a second discharge valve, a filter cabin, a second spray pipe, an air cooler, a radioactivity monitor, a passive residual heat discharge water tank, a first stop valve and a second stop valve. By arranging a plurality of radioactive removal means which are connected in series, including two-stage bubbling washing, static mixer bubble cutting, efficient metal fiber filtering, silver zeolite filtering and the like, efficient removal of airborne radioactive substances (aerosol, inorganic iodine and organic iodine) can be realized; and the radioactive influence of overpressure discharge of the containment on the environment under the condition of serious accidents is reduced. The air cooler is arranged on the filtering and discharging pipeline to condense discharged steam, condensate returns to the filtering cabin by means of the gravity difference, and long-term passive effective operation of the water scrubber can be achieved.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to a solidification method. According to the method, a conveying and jacking device is used for conveying a material containing device to enable the material containing device to receive powdery materials, a clamping and transferring device and a lifting device are used for conveying the material containing device completing feeding into a material processing device to enable the powdery materials to be partially molten, and a pressurizing device is used for pressing and compacting the partially molten materials; and finally, ingot-shaped solid materials are formed in the material containing device, then the lifting device and the clamping and transferring device are utilized again to transfer the material containing device to the conveying and jacking device so as to transfer the ingot-shaped solid materials, in this way, the process from powder feeding to ingot forming of the materials is conducted in the material containing device, the situation that a material container is replaced in the midway is avoided, and the production efficiency is improved. Operation steps are simplified; and the clamping and transferring device, the lifting device and the conveying and jacking device all participate in the front process and the rear process of material treatment, so that reuse of equipment parts is achieved, and the equipment composition is simplified.

The invention belongs to the technical field of radioactive wastewater treatment, and particularly relates to composite aerogel for adsorbing Cs < + > and Sr < 2 + > in radioactive wastewater under an acidic condition and a preparation method of the composite aerogel. The preparation method of the composite aerogel comprises the following steps: (1) synthesizing ammonium phosphomolybdate / sodium alginate aerogel; (2) growing ZIF-8 on the surface of the ammonium phosphomolybdate / sodium alginate aerogel; and (3) modifying the surface of the material obtained in the step (2) by using potassium permanganate to generate MnO2, thereby obtaining the composite aerogel. The composite aerogel can efficiently adsorb Cs < + > and Sr < 2 + > in wastewater to realize efficient co-adsorption of double ions, and has the advantages of low energy consumption, high selective separation efficiency, capability of carrying out one-step curing separation, no secondary pollution and capability of effectively avoiding the defects of redundant separation operation and large waste liquid amount in a traditional method, and a high-capacity and easily-recycled adsorbent scheme is provided for radioactive wastewater treatment.

The invention provides high-strength retarded magnesium phosphate cement as well as a preparation method and application thereof, and belongs to the technical field of magnesium phosphate cement. The high-strength retarded magnesium phosphate cement provided by the invention is prepared from the following raw materials in parts by mass: 60 to 95 parts of dead burned magnesia powder, 20 to 50 parts of phosphate, 3 to 15 parts of a composite retarder, 5 to 20 parts of an admixture, 8 to 14 parts of fly ash microspheres, 1 to 2 parts of carbon nanotubes, 1 to 5 parts of carbon fibers and 5 to 30 parts of water, the composite retarder comprises sodium tripolyphosphate, zinc acetate, EDTA (Ethylene Diamine Tetraacetic Acid) disodium and polyacrylic acid; the admixture comprises phosphorus slag powder and silica fume. The result of the embodiment shows that the setting time of the high-strength delayed-setting magnesium phosphate cement provided by the invention is controllable between dozens of minutes and dozens of hours, meanwhile, the compressive strength of the magnesium phosphate cement 28d is greater than 90MPa, and the magnesium phosphate cement has excellent mechanical properties.

The invention relates to an adsorbent and a preparation method and application thereof, the adsorbent comprises a polymer matrix and a nanofiller uniformly embedded in the polymer matrix, the polymer matrix comprises a calcium / boron cross-linked polyvinyl alcohol-sodium alginate blend, and the nanofiller is sulfonic acid / carboxylic acid functionalized graphene oxide; the mass fraction of the nano filler in the adsorbent is 0.05%-0.60%; wrinkles and irregular hole structures are distributed on the surface of the adsorbent. The adsorbent is used for removing tritium in water and is high in adsorption capacity, stable in structure and good in recycling performance. The removal rate of tritium in the single-stage adsorption process is greater than 8.5%, and the removal rate of tritium in the third-stage adsorption process is 19.4-57.7%.

The invention discloses an NZP-high-entropy (Ln1 / n) PO4 monazite type multiphase ceramic solidified body and a preparation method thereof, the chemical general formula of the NZP-high-entropy (Ln1 / n) PO4 monazite type multiphase ceramic solidified body is (1-x) Sr0. 5Zr2 (PO4) 3-x (Ln1 / n) PO4, x represents molar percentage, the value range is 0.1-0.9, x represents molar percentage, and the value range is 0.1-0.9. The NZP-high-entropy (Ln1 / n) PO4 monazite type multiphase ceramic solidified body is NZP-high-entropy (Ln1 / n) PO4 monazite type multiphase ceramic solidified body. N represents the number of element types of Ln lattice sites in the high-entropy (Ln1 / n) PO4 monazite type, and n is an integer and is larger than or equal to 5 and smaller than or equal to 7; the Ln element types comprise La, Nd, Sm, Eu, Gd, Ho, Er, Sr0. 5Zr2 (PO4) 3 and (Ln1 / n) PO4, and the molar ratio of the Ln element types to the Sr0. 5Zr2 (PO4) 3 to the (Ln1 / n) PO4 can be freely regulated and controlled. The NZP-high-entropy (Ln1 / n) PO4 monazite type multiphase ceramic solidified body adopts an in-situ preparation process, and integration of crystal phase synthesis and sintering densification can be realized. The preparation method comprises the following steps: uniformly mixing the raw materials, pretreating, adding a sintering aid, mixing again, granulating and aging the obtained powder, molding, removing plastic, and sintering to obtain the NZP-high-entropy (Ln1 / n) PO4 monazite type composite ceramic solidified body. The preparation process disclosed by the invention has the advantages of flexible composition design, capability of simultaneously curing various fission products and (sub) actinide series nuclides, short preparation period, low production energy consumption, high product compactness and the like.

The invention discloses a tritiated waste ash purification method and system based on cooperation of multistage adsorption and low-temperature distillation. The method comprises the following steps: S1, sorting treatment; s2, acid leaching treatment; the waste ash to be treated is subjected to acid leaching treatment, and acid leaching slurry is obtained; s3, carrying out separation treatment; carrying out separation treatment on the acid leaching slurry to obtain acid leaching residues and leachate; s4, adsorption treatment; carrying out adsorption treatment on the leachate to obtain penetrating liquid; s5, catalytic treatment; performing catalytic treatment on the penetrating liquid to obtain tritiated water and catalytic treatment tail gas; and S6, carrying out adsorption treatment on the catalytic treatment tail gas. According to the tritiated waste ash purification method, multi-stage adsorption and low-temperature distillation cooperative treatment is adopted, and the tritiated waste ash purification efficiency is greatly improved. According to the tritiated waste ash purification system, pretreatment, adsorption-catalysis and rectification concentration unit independent packaging are achieved through modular design, and rapid disassembly and assembly and multi-line parallel treatment are supported.

The invention discloses a radioactive waste liquid treatment method and system for the nuclear medicine department, and belongs to the technical field of waste liquid treatment of the nuclear medicine department. The method comprises the steps that waste liquid is discharged into a pre-storage container, concentration detection and nuclide type detection are conducted, and the waste liquid with the concentration detection result lower than a specified limit value is directly discharged into a medical waste water pipeline; other waste liquids are classified and discharged into the corresponding decay tanks according to the half-life periods of nuclide types, the storage time of the waste liquids in the decay tanks is different according to different half-life periods, and the waste liquids in the corresponding decay tanks are discharged in time after the storage time is reached. According to the invention, the amount of the waste liquid actually entering the decay tank is reduced from the source end, and the waste liquid is discharged into the decay tank in a classified manner based on nuclide types, so that the storage time of the waste liquid corresponding to nuclides with short half-life periods in the decay tank can be shortened, the discharge efficiency of most of the waste liquid is improved, and the amount of the waste liquid in the decay tank is effectively reduced.

The invention relates to the technical field of transmission, in particular to an annular transmission mechanism and a nuclear waste glass curing forming device. In the annular transmission mechanism, a reference shaft and a ratchet wheel are coaxially and fixedly connected, and the reference shaft is provided with a matching end used for transmission matching. The blocking arm is fixedly connected to the end, away from the reference shaft, of the swing arm. The first pawl is rotationally matched with the end, away from the reference shaft, of the swing arm and matched with a torsional spring so that the first pawl can be attached to the ratchet wheel. When the first pawl reciprocates along the ratchet wheel, the ratchet wheel can be intermittently driven. When the first pawl does reciprocating motion along the ratchet wheel, ratchets of the ratchet wheel can periodically push the first pawl to the side where the blocking arm is located, so that the first pawl can periodically extrude the pressing part. The temperature control can be synchronously completed while transmission is realized, and the matching degree between the transmission and the temperature control is further improved.

A radioactive waste supercritical water oxidation nuclide removal reaction device comprises a cooling water jacket, a pressure-bearing type reaction cavity is formed in the cooling water jacket, a flow guide cavity is formed in the pressure-bearing type reaction cavity, a nuclide salt removal core area is arranged in the center of the flow guide cavity, and an end cover material inlet area is arranged at the top of the nuclide salt removal core area. Waste heat recovery devices are respectively arranged in the flow guide cavity and the pressure-bearing reaction cavity; in a supercritical water oxidation environment, efficient degradation of radioactive wastes is realized, and nuclides are separated by using the characteristic of extremely low solubility of supercritical water to nuclide salts and the thermal wall adhesion effect of inorganic salts and by adopting a multi-stage filtering method, so that migration of the radionuclide salts is limited in a core area in a reactor, and the radionuclide salts are efficiently degraded. Nuclide contamination of large-size key parts such as a pressure-bearing wall and an end cover of the reactor is avoided, and meanwhile, mechanical devices such as a stirring device and a scraping brush are not additionally arranged in the reactor, so that the minimization of radioactive waste generated after the device is decommissioned is ensured; the method has a remarkable application value in the field of supercritical water oxidation treatment of radioactive wastes.

The invention relates to a universal method for co-adsorbing perrhenate or pertechnetate by using cationic dye modified activated carbon, and belongs to the technical field of water treatment. In the system provided by the invention, the cationic dye modified activated carbon is used as an adsorbent of perrhenate or pertechnetate, and the cationic dye / activated carbon composite material realizes efficient removal of pollutants by co-adsorbing the perrhenate or pertechnetate in sewage. According to the invention, 12 activated carbon is used as a porous carrier, and after five different cationic dyes are respectively adsorbed, perrhenate radicals can be effectively adsorbed. Particularly, after methylene blue dye is adsorbed, perrhenic acid radicals can be quickly adsorbed within an extremely short time, and the adsorbent has the advantages of large adsorption capacity, good pH stability, high selectivity, good radiation resistance, low cost and the like, and can be applied to actual environmental sewage.

The invention discloses a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The shot blasting particle internal circulation regeneration system comprises a smelting furnace, a melting and pumping machine and a shot blasting machine which are sequentially used according to a closed-loop sequence, a smelting cavity is formed in the smelting furnace; the melt extraction machine comprises a bottom moving mechanism, a middle lifting mechanism and an upper executing mechanism which are sequentially connected from bottom to top. The upper executing mechanism comprises a rotary driving assembly and a melting tap; the rotary driving mechanism is mounted at the upper end of the middle lifting mechanism and is associated with the melting tapping head so as to drive the melting tapping head to rotate, molten steel in a smelting cavity of the smelting furnace is thrown out in a liquid column form when the melting tapping head rotates, and shot blasting particles are obtained after the liquid column is cooled and solidified in the flying process and falls to the ground; when the shot blasting machine works, shot blasting particles manufactured by a melting and pumping machine are used. According to the method, an internal recycling regeneration system of radioactive contamination metal and shot blasting particles is constructed, the radioactive contamination metal is converted into self-consumption shot blasting particles, recycling regeneration is achieved, and the increment of radioactive waste is remarkably reduced.

The invention provides a portable marine radionuclide rapid collection and enrichment device, and relates to the technical field of nuclear energy safety and environmental protection. The portable marine radionuclide rapid collection and enrichment device comprises a box body, a first top cover and a control panel, the first top cover is rotatably connected to the upper end face of the box body, the control panel is arranged at the center of the upper end face of the first top cover, and an electromagnetic valve is fixedly connected to the center of the lower end face of the box body. The output end of the electromagnetic valve penetrates through the lower end face of the box body to the lower inner wall of the box body, the end is fixedly connected with an adjusting structure, and the input end of the electromagnetic valve is sleeved with a filtering structure in a threaded mode. The electromagnetic valve and the first conveying pump are controlled to be started, water flow enters the mixer through the sleeve and the electromagnetic valve, and after the water flow extrudes the blades when passing through the blades, the blades and the shaft rod rotate to drive the two brush rods to rotate, so that foreign matter is prevented from blocking the filter screen, and it is guaranteed that seawater can rapidly enter the mixer.

The invention relates to a waste liquid treatment device for automatically separating radionuclides. The waste liquid treatment device comprises a first waste liquid collection passage and a second waste liquid collection passage, an upstream liquid supply channel shared by the two channels comprises an injection pump and a multi-way valve, and the injection pump inputs liquid into the multi-way valve. The first waste liquid collecting channel directly guides cleaning liquid, replacement liquid and the like which do not need to be reserved into a waste liquid barrel through a first output port of the multi-way valve. The second waste liquid collecting channel is sequentially connected with a plurality of resin columns, a waste liquid tank, a peristaltic pump and a waste liquid barrel through a second output port of the multi-way valve, waste liquid generated by the resin columns firstly enters the waste liquid tank for temporary storage, and when the liquid level of the waste liquid tank reaches a preset threshold value, the peristaltic pump automatically pumps and discharges the waste liquid into the waste liquid barrel for centralized collection. The device can distinguish reserved liquid from waste liquid according to steps, realizes automatic flow division, temporary storage and discharge of the waste liquid, avoids manual pouring of the waste liquid halfway, ensures continuous operation of a long-time and multi-channel separation process, and reduces the risk of personnel exposure in a radioactive waste liquid treatment process.

The invention relates to a shot blasting particle internal circulation regeneration method for decontaminating radioactive contaminated metal, which is applied to a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The invention discloses a shot blasting particle internal circulation regeneration system for decontaminating radioactive contaminated metal. The shot blasting particle internal circulation regeneration system comprises a smelting furnace, a melting and pumping machine and a shot blasting machine which are sequentially used according to a closed-loop sequence, the method comprises the following steps: raw material pretreatment; smelting and decontaminating the raw materials; preparing pills by a melt extraction machine; shot-blasting and decontaminating the raw materials; and after decontamination, smelting and pelleting. The method has the advantages that radioactive contamination metal is converted into self-consumption shot blasting particles, cyclic regeneration is achieved, radioactive waste increment is remarkably reduced, near-zero emission of nuclear facility decommissioning waste is promoted, and the requirement for minimization of IAEA radioactive waste is met.

To provide a technique capable of contributing to environmental load reduction while securing performance as a water purification filter.SOLUTION: The water purification filter 11 satisfies at least one of the conditions that the increase in CO2 on the ground surface due to CO2 released at the time of disposal is not more than 240L per kilogram and that the use rate of petroleum-derived raw materials is not more than 15%.SELECTED DRAWING: Figure 3

The invention provides a method for accurately regulating and controlling pores of an MXene material by utilizing a phosphonic acid ligand, which mainly comprises the following key steps of: directionally removing a main group element (A) layer of an MAX precursor by wet etching to obtain lamellar MXene, and then introducing a protonated quaternary amine compound intercalator to strip the MXene. And finally, carrying out functional modification and conversion by adopting a phosphonic acid ligand, and stably introducing phosphonic acid groups between layers and on the surface of MXene through solvothermal reaction to realize accurate regulation and control of interlayer spacing. The prepared material can realize efficient adsorption of uranyl in an acidic environment, shows high selectivity, high adsorption capacity and good acid stability and regeneration capacity to uranyl, provides a stable and efficient selective adsorption solution for treating high-acidity uranium-containing nuclear wastewater, and has a remarkable industrial application prospect.

The invention relates to a common glass curing method for radioactive incineration ash and a contaminated glass fiber filter material, which comprises the following steps of: melting and curing a raw material containing the radioactive incineration ash and the contaminated glass fiber filter material by adopting a method I or a method II to prepare a glass cured body; according to the first method, raw materials of the filter material containing the radioactive incineration ash and the contaminated glass fiber comprise 0 wt%-30 wt% of the radioactive incineration ash and 70 wt%-100 wt% of the contaminated glass fiber filter material, and the melting temperature ranges from 1100 DEG C to 1400 DEG C; according to the second method, raw materials of the filter material containing the radioactive incineration ash and the contaminated glass fiber comprise 0 wt%-40 wt% of the radioactive incineration ash, 30 wt%-60 wt% of the contaminated glass fiber filter material and 15 wt%-50 wt% of an additive, and the melting temperature ranges from 900 DEG C to 1300 DEG C. According to the method, the glass solidified body meeting the disposal requirement can be effectively and stably obtained on the premise that the incineration ash component fluctuates greatly and the fly ash component contained in the contaminated glass fiber filter material is uncertain.

The embodiment of the invention relates to the field of radioactive waste treatment, in particular to curing equipment. According to the curing equipment provided by the embodiment of the invention, the powdery materials are conveyed into the material containing device through the vacuum feeding device, and the material containing device is transferred to the lifting device through the clamping and transferring device, so that the material containing device is conveyed into the material processing device through the lifting device; the sealing device is used for sealing the material treatment device, so that the material reaction process is carried out in an environment with relatively good sealing performance; the pressurizing device is used for compacting the materials so as to obtain solid materials which are easier to transfer and process compared with powdery materials; the vacuum feeding device, the conveying and jacking device, the clamping and transferring device, the lifting device, the material treatment device and the pressurizing device are fixed to different positions of the body, enough space is provided for all treatment links of materials, the operation sequence of curing treatment is met, the process is simplified, and the treatment efficiency is improved.

The invention relates to the technical field of pipeline decontamination, in particular to an online pipeline ultrasonic decontamination device and method suitable for various pipe diameters, and the online pipeline ultrasonic decontamination device comprises a numerical control generator, a transducer, an amplitude-change pole, an adaptive clamp, an online monitoring device and other key components. And through the designed adaptive clamp, the device can act on pipelines with various pipe diameters and can move along the pipelines, and the decontamination requirements in different scenes are met. The online ultrasonic decontamination device is suitable for maintenance and cleaning work of pipelines with different pipe diameters in nuclear power facilities, and has important significance in improving the safety of the nuclear facilities and guaranteeing radiation protection for operators. The problem that an ultrasonic device is poor in applicability is effectively solved, meanwhile, the flexibility of the device is guaranteed, effective online decontamination of pipelines with various pipe diameters can be achieved through a single set of device, the decontamination cost of radioactive contamination of nuclear facility pipelines is effectively reduced, online efficient decontamination of radioactive contamination deposited in the pipelines is achieved, and the service life of the pipelines is prolonged. The safe and stable operation of the reactor is ensured, and the radiation risk of operators is reduced.

The invention provides a polyimine membrane material as well as a preparation method and application thereof in iodine adsorption, and relates to the technical field of adsorption materials. The preparation method comprises the following steps: mixing a cross-linking agent, a dialdehyde monomer, a diamine monomer and an aprotic solvent to carry out Schiff base reaction, and removing the solvent from the obtained polyimine solution to form a film, so as to obtain a polyimine film material; the cross-linking agent comprises 2, 6-bis (3 ', 4'-diaminophenyl)-4-phenylpyridine and / or tris (2-aminoethyl) amine. The prepared polyimine membrane material has excellent iodine adsorption capacity and adsorption stability; due to the dynamic imine bond, the broken polyimide film material can be remodeled and recovered under the hot pressing condition, and the characteristic of easiness in recovery is realized; the polyimine membrane material also has excellent mechanical properties. Meanwhile, compared with a powder iodine adsorption material, the membrane-based material overcomes the characteristic of easiness in caking, and shows good cost effectiveness and user friendliness; moreover, the polyimine can be prepared only at room temperature, and the process is simple and convenient.