680 results about "Radioactive waste" 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 embodiment of the invention relates to the field of radioactive waste treatment, in particular to lifting feeding equipment and curing equipment. According to the lifting feeding equipment provided by the embodiment of the invention, the conveying jacking device drives the material containing device to move in different directions, so that the material containing device abuts against the vacuum feeding device, the powdery materials can be conveyed to the material containing device from the vacuum feeding device, the powdery materials can be prevented from escaping through jacking communication, and the working efficiency is improved. And material waste and operation space pollution are avoided. According to the curing equipment provided by the embodiment of the invention, the material containing device is moved through the lifting feeding equipment, and the powdery materials are conveyed to the material containing device, so that the powdery materials can be prevented from being scattered; and meanwhile, the material containing device containing the powdery materials can reach other processing stations by moving the material containing device into or out of the containing space so as to carry out the next processing procedure.

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 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 utility model relates to a nuclear power high-radiation object containing device and containing and transferring equipment. The containing and transferring equipment comprises the nuclear power high-radiation object containing device. The nuclear power high-radioactivity storage device is specially designed for underwater operation, and can safely store and seal high-radioactivity waste under the condition that normal operation of a reactor is not affected. The sealing mechanism ensures that the radioactive substance storage space is completely sealed in the transferring and long-time storage process, radioactive substances are prevented from leaking, and the safety of the treatment process is greatly improved. And secondly, the torque input end allows torque to be input through an external tool to achieve rotation of the lock cylinder, so that the closing or opening action is rapidly and effectively completed, the operation process of containing and closing the radioactive substances is simplified, and the containing and closing efficiency of the radioactive wastes is improved.

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 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 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.

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 belongs to the technical field of radioactive site waste treatment, and particularly relates to a discharging device of an end receiving hopper of a vertical feeding shearing machine. The device comprises an end receiving hopper and a rotary opening and closing mechanism, the end receiving hopper is of a funnel-shaped structure, and a rotary opening and closing mechanism is connected to a discharging opening in the lower end of the end receiving hopper. The rotary opening and closing mechanism comprises a guide support, a rotary disc and a plurality of blades. Communicated holes are formed in the middle of the guide bracket and the turntable and are communicated with the discharge hole; a plurality of sliding grooves in one-to-one correspondence with the blades are formed in the guide bracket; a guide groove is formed in the upper end of the turntable; pins are arranged at the upper ends of the blades and are fixed in the sliding chutes in a sliding manner; guide columns are arranged at the lower ends of the blades and fixed in the guide grooves in a sliding mode, and the multiple blades seal or open the holes by rotating the rotary disc. According to the device, the process of clamping the stub by a manipulator is omitted, the transfer efficiency is greatly improved, the failure rate of the hydraulic device of the end receiving hopper is reduced, and the operating rate of the shearing machine is improved.

The invention belongs to the field of light low-carbon concrete, and discloses hydraulic low-carbon concrete containing barium sulfate barite as well as a preparation method and application of the hydraulic low-carbon concrete. The concrete is prepared from 42.5-grade Portland cement, barium sulfate barite powder, modified polypropylene fiber, industrial waste residue lightweight aggregate, boron carbide powder, nano silicon dioxide, a polycarboxylate superplasticizer, a composite exciting agent and water according to specific parts by weight. Wherein the barium sulfate barite powder is subjected to graded proportioning and calcination activation, the modified polypropylene fiber is treated by plasma and a silane coupling agent, the industrial waste residue lightweight aggregate is formed by compounding fly ash ceramsite and steel slag microbeads, and the composite exciting agent is composed of specific components. The concrete is high in compressive strength, low in dry density, excellent in neutron shielding and gamma ray attenuation performance and low in chloride ion diffusion coefficient. The preparation method comprises the steps of premixing modification, gradient stirring, vibration compaction and steam curing. The concrete is suitable for construction of a nuclear reactor containment, a radioactive waste repository and a nuclear medicine protection wall.

The disclosure belongs to the technical field of inorganic non-metallic cementitious materials, and provides a phospho-alumino-silicate inorganic polymer, and a preparation method and use thereof. The phospho-alumino-silicate inorganic polymer includes the following raw materials in parts by weight: 50 parts to 67 parts of a precursor raw material, 33 parts to 50 parts of an activator, and water; where the precursor raw material includes metakaolin and activated calcium oxide; the activated calcium oxide accounts for 3% to 15% of a weight of the precursor raw material; and the activator includes a phosphoric acid solution. The phospho-alumino-silicate inorganic polymer obtained by the above formula could not only meet the pH value less than 11 of a sealing material of the geological repository for a high-level radioactive waste, but also could effectively support cracks and broken rocks.

To provide a radiopharmaceutical production apparatus and the like capable of reducing the generation amount of radioactive waste.SOLUTION: A radiopharmaceutical production apparatus 51 comprises: a cassette 20 which has a reagent supply port, a radionuclide supply port, a drug solution outlet, a reaction unit, a purification column, and flow paths respectively connecting the reagent supply port and the reaction unit, the radionuclide supply port and the reaction unit, the reaction unit and the purification column, and the purification column and the drug solution outlet; and a cassette mounting unit to which the cassette 20 is attachable and detachable.SELECTED DRAWING: Figure 3

The invention provides a test device and method for simulating seepage, heat transfer, chemistry and stress of high-level radioactive waste disposal, the test device comprises a test box body, a rock-soil body model is arranged in the test box body, the rock-soil body model is composed of sandstone and bentonite, and a heat source is arranged in the middle of the bentonite; a fracture network is arranged in the rock-soil body model, a thermometer, a water pressure gauge and a strain gauge are placed in the fracture network and are in signal connection with a data acquisition instrument, and the data acquisition instrument is in signal connection with a data processing computer; and the test box body is also connected with a fluid supply system. Through repeated model tests, quantitative and qualitative analysis can be carried out on the influence of heat source temperature, different-configuration fracture water seepage paths, fracture water seepage speeds, fracture water chemical properties and inter-fracture water seepage interaction on a rock-soil body model temperature field, a water pressure field and a displacement field; the method has important significance for improving safe disposal of high-level radioactive waste, and is economical and practical.

To provide a radioactive waste discharge plan preparation support system capable of efficiently processing and managing radioactive waste.SOLUTION: A radioactive waste discharge planning support system includes a storage unit that stores information on an amount of radioactivity of radioactive waste and a measurement date of the amount of radioactivity, and a discharge planning unit that predicts a time when the amount of radioactivity becomes equal to or less than a specified value based on the information on the amount of radioactivity and the measurement date of the amount of radioactivity stored in the storage unit for the radioactive waste having the amount of radioactivity equal to or more than the specified value, and creates a discharge plan of the radioactive waste based on the predicted time.SELECTED DRAWING: Figure 1

The invention discloses a method and device for reusing boric acid in waste liquid of a nuclear power plant, and the method comprises the following steps: carrying out the pretreatment of radionuclides in the waste liquid of the nuclear power plant, and obtaining first radioactive waste liquid; carrying out nanofiltration on the first radioactive waste liquid to respectively obtain separated first produced water and first concentrated water; the first produced water is subjected to first boron concentration through reverse osmosis, separated second produced water and second concentrated water are obtained, the second concentrated water is a boric acid concentrated solution, and the second concentrated water is reused in the nuclear power plant; the second produced water is subjected to second-stage boron concentration through second-stage reverse osmosis, third produced water and third concentrated water which are separated are obtained, and the third produced water is produced water meeting the preset discharge condition. According to the method, deep purification treatment is conducted on the waste liquid of the nuclear power plant, resource recycling and reuse of boric acid are achieved while the emission requirement is met, and the reuse concentration of boric acid of different reactor types can be met by adjusting technological parameters.

The invention provides an intelligent treatment system for radioactive waste liquid. The intelligent treatment system comprises the following steps: acquiring basic working data of a radiation subject, analyzing estimated waste liquid radiation activity and estimated waste liquid generation amount in a specified time period to construct a waste liquid collection measure for waste liquid collection, and calling a corresponding waste liquid detection mode according to the estimated waste liquid radiation activity, the waste liquid is sampled and detected in a waste liquid detection mode, the nuclide activity value of the waste liquid is determined, the waste liquid is conveyed to a treatment area of a corresponding grade based on the nuclide activity value to be subjected to active treatment, nuclide activity value change information of the waste liquid is determined according to supervision data in the active treatment process, and after the active treatment of the waste liquid is completed, the waste liquid is processed. According to nuclide activity value change information, after-treatment radioactivity of a generated treatment object is analyzed, the generated treatment object is stored, and an intelligent treatment system integrating waste liquid collection, radioactivity monitoring, separation treatment and environment-friendly emission is constructed.

The invention discloses a miniaturized movable radioactive waste sorting and measuring device which comprises a sorting robot, a bag breaking mechanism arranged on the sorting robot, a measuring box, a radiation detection mechanism, a grabbing mechanism, a visual mechanism and a control mechanism connected with the sorting robot, the bag breaking mechanism, the measuring box, the grabbing mechanism and the visual mechanism. Automatic identification and unmanned sorting of the to-be-sorted radioactive waste are achieved based on the robot, and deployment flexibility and operation automation are achieved through autonomous movement of the robot. And moreover, long-acting operation is achieved, personal injury or result errors caused by manual sorting are reduced, the sorting efficiency is high, and the final disposal amount and disposal cost of the radioactive waste are reduced.

The invention belongs to the technical field of radioactive waste treatment, and discloses radioactive filter waste filter element frame separation equipment and method.The radioactive filter waste filter element frame separation equipment comprises a conveying frame, a first frame, a cutting assembly and a conveying assembly, a second frame is installed on the back face of the conveying frame, and the cutting assembly is installed at the top of the conveying frame; and a conveying assembly is slidably installed at the top of the conveying frame, an air extracting pump is installed on the inner wall of the cutting assembly, a purifying box is installed at the bottom of the conveying frame, the purifying box is filled with purifying liquid, and the output end of the air extracting pump extends into the purifying box. The filter element and the frame can be separated conveniently by arranging the first cavity and other structures, the electric heating wire is powered by the conducting rod through the distribution box, the filter element is heated by the clamping device, and therefore sealant between the filter element and the frame is heated and softened, and subsequent separation is facilitated.

The invention discloses a preparation method of a PVDF-Q-ZIF-67 / POTS membrane and application of the PVDF-Q-ZIF-67 / POTS membrane in treatment of radioactive waste liquid of a nuclear power plant, and the preparation method comprises the following steps: firstly, blending PVA (polyvinyl alcohol), Que (quercetin) and PVDF (polyvinylidene fluoride) for electrostatic spinning to obtain a PVDF-Q hydrophilic layer, then carrying out electrostatic spinning on the blended LiCl and PVDF to obtain a PVDF base membrane, and then carrying out electrostatic spinning on the PVDF base membrane by adopting ZIF-67, POTS (1H, 1H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H, 2H The method comprises the following steps of: coating a PVDF (Polyvinylidene Fluoride) base membrane with a ZIF-67 / POTS super-hydrophobic coating by using a PVDF-Q-ZIF-67 / POTS super-hydrophobic coating as a raw material, assembling to synthesize a PVDF-Q-ZIF-67 / POTS membrane, and finally introducing the radioactive waste liquid into a direct contact type membrane distillation device adopting the PVDF-Q-ZIF-67 / POTS membrane for treatment, so that the concentration of the radioactive waste liquid and the efficient separation of nuclides can be realized. The PVDF-Q-ZIF-67 / POTS membrane is applied to treatment of nuclear power station radioactive waste liquid, after direct contact type membrane distillation, the flux of the PVDF-Q-ZIF-67 / POTS membrane can be kept stable for a long time, the concentration multiple is high, the nuclide rejection rate is larger than or equal to 99.9%, and the PVDF-Q-ZIF-67 / POTS membrane is stable in chemical property, good in pollution resistance and good in application prospect in the fields of nuclear power stations, nuclear fuel plants and the like.

The invention relates to the field of metal corrosion behavior monitoring and characterization, in particular to a rapid evaluation method for a material corrosion rate and influence factors in a high-level radioactive waste geological disposal environment. According to the method, two indexes are obtained based on electrochemical impedance spectroscopy measurement and relaxation time distribution analysis, namely an impedance modulus value Z0.01 Hz value corresponding to 0.01 Hz and a time constant log (tau / s) value corresponding to a dissolved oxygen reduction reaction. The Z0.01 Hz value and the log (tau / s) value when the material enters anaerobic corrosion from aerobic corrosion are taken as critical points, whether the material is in an aerobic corrosion state, a low-oxygen corrosion state or an anaerobic corrosion state is judged according to the measured Z0.01 Hz value and log (tau / s) value, and the coverage degree of corrosion products on the surface of the material and whether oxygen leakage occurs in a treatment environment are also judged. The method is suitable for rapidly evaluating the material corrosion rate and influence factors in the high-level radioactive waste geological disposal environment, and has the characteristics of simplicity, high operability, high accuracy and good long-term stability.

The invention discloses a radioactive waste liquid surface pollution multipoint array detection system and method, and relates to the technical field of nuclear radiation detection. The radioactive waste liquid surface pollution multipoint array detection system comprises a main body fixing frame, a mobile control device, a detector and an upper computer, a plurality of mounting holes arranged in a planar array are formed in the main body fixing frame; the movement control device controls the main body fixing frame to move; the plurality of detectors are mounted in the mounting holes of the main body fixing frame; the upper computer is used for regulating and controlling parameters of the CMOS sensor and storing, displaying, analyzing and processing frame images. The radioactive waste liquid storage tank liquid level pollution monitoring method is applied to a radioactive waste liquid surface pollution multipoint array detection system and is used for monitoring alpha and beta pollution areas of a radioactive waste liquid storage tank liquid level. The whole liquid level area of the radioactive waste liquid storage tank is covered at a time through the detachable detector group arranged in the plane array, and a pollution distribution panorama can be obtained through single-time measurement.

The invention discloses functionalized graphene for removing tritium from radioactive waste liquid and a preparation method and application of a graphene film, the functionalized graphene is a flaky substance formed by stacking lamellar structures, and the distance between the stacked lamellar structures is 7.5-8.7. The preparation method comprises the following steps: preparing graphene oxide powder; performing sulfonation on the graphene oxide powder to obtain sulfonated graphene aerogel; performing carboxylation on the graphene oxide powder to obtain carboxylated graphene; and mixing and stirring the sulfonated graphene aerogel and carboxylated graphene to obtain the functionalized graphene. The tritium in the tritium-containing liquid is separated by utilizing the membrane formed by the functionalized graphene, and the tritium removal technology has the advantages of mild reaction conditions, low energy consumption, easiness in large-scale production and the like.

The invention relates to the technical field of transmission, in particular to a transmission mechanism, a linear forming device and a high-level liquid waste glass sample preparation system. The first driving wheel is connected with the driving shaft. The second matching rod is in threaded fit with the matching sleeve, and the first matching rod is matched with the second matching rod. The first matching rod is provided with a rotating piece, the first extension rod is connected to the driving shaft, and the included angle between the first extension rod and the driving shaft is larger than 0 degree and smaller than 90 degrees. The first connecting rod is connected between the first extension rod and the rotating piece. The first driving wheel is used for transmitting power outwards, and the end, away from the first matching rod, of the second matching rod is used for installing an execution assembly. According to the transmission mechanism, transmission is achieved, meanwhile, accurate control over the execution assembly can be synchronously achieved, the cooperative matching degree between the transmission assembly and the execution assembly is further improved, a needed power source is simpler, and the structure is simpler.

According to one embodiment of the present disclosure, there is provided a plasma curtain generator comprising: a cylindrical magnet; a cylindrical copper tube disposed inside the cylindrical magnet; and at least one electrode rod disposed along a central axis of the cylindrical copper tube, wherein a high voltage is applied between the cylindrical copper tube and the electrode rod to continuously generate plasma in an atmospheric pressure state, and the cylindrical magnet provides a magnetic force for maintaining the plasma within a certain space inside the cylindrical copper tube. The plasma curtain generator may be installed in a chimney into which an exhaust gas flows from the incineration to reduce the pollutants contained in the exhaust gas in incineration facilities treating household or industrial waste, or in incineration facilities treating low- and intermediate-level radioactive waste.

The invention discloses a radioactive waste treatment method which comprises the following steps: firstly, treating a waste ventilation filter element to obtain a glass substrate, and then carrying out plasma high-temperature melting treatment on to-be-treated miscellaneous dry waste by adopting a glass material containing the glass substrate to obtain glass-like molten slag. The radioactive waste treatment method is ingenious in conception and simple and reasonable in step, the waste ventilation filter element subjected to cement fixation treatment is reused, the waste treatment cost is reduced, and the waste volume reduction effect is effectively improved. The invention further provides a radioactive waste treatment system and a waste ventilation filter element crushing and packaging system.

The invention discloses a preparation method and application of a melamine modified collagenous fiber iodine adsorbent, and relates to the technical field of nuclear medical radioactive waste treatment. The preparation method comprises the following steps: activating collagen fibers and modifying melamine; wherein the melamine modification comprises the following steps: taking the activated collagenous fiber, adding water, melamine and a dialdehyde cross-linking agent, and stirring at 35-45 DEG C for 6-8 hours to obtain the melamine modified collagenous fiber iodine adsorbent. According to the application, the prepared melamine modified collagenous fiber iodine adsorbent is used for adsorbing radioactive iodine. After melamine grafting, the nitrogen content of the collagenous fiber is remarkably increased, the collagen fiber has more prominent adsorption capacity on iodine steam and iodine in a solution, and an effective strategy is provided for removal and collection of radioactive iodine such as medical wastewater and radioactive waste liquid.

The utility model is applicable to the field of nuclear waste treatment, and discloses a shielding device for high-radioactivity waste storage and transfer of a nuclear power plant, which comprises an outer barrel, a barrel cover, a hinge locking component and an inner barrel, the inner barrel is arranged in the outer barrel, the outer barrel is provided with an outer wall and an inner wall, the inner wall is fit with the inner barrel in shape, a radiation-proof material is filled between the inner wall and the outer wall, the outer wall is provided with a first lifting lug extending outwards, the barrel cover is arranged on the upper portion of the outer barrel, and a second lifting lug is arranged on the barrel cover. After radioactive waste is loaded into the inner barrel and the inner barrel is sealed, the inner barrel is then loaded into the outer barrel, the barrel cover and the outer barrel are locked through the hinge locking assembly, then an operator carries the outer barrel through connection of the first lifting lug and mechanical equipment, and when the barrel cover is opened and closed, the second lifting lug or a lifting appliance on the barrel cover can be selected according to an existing clamp and tool. The whole shielding device is simple in structure, the inner barrel, the outer barrel and the barrel cover are convenient and simple to install and carry, and the radiation time of operators is shortened.