1063 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 invention discloses a preparation method and protection application of a luminous iodine adsorbent, and relates to the technical field of radioactive waste gas and waste liquid treatment. The method comprises the following steps: jointly dissolving an organic ligand and metal ions in a solvent to obtain a mixed solution, carrying out room-temperature reaction on the mixed solution, and assembling to obtain the luminous MSOFs adsorbent, wherein the organic ligand is a sulfydryl ligand with a nitrogen heterocyclic ring or a phenylphosphine derivative; the ligand central atom comprises gold, silver, copper, platinum, palladium, iron, aluminum, nickel or cobalt. The prepared iodine adsorbent and the protection device are excellent in adsorption capacity, low in cost, capable of being rapidly and massively synthesized, high in adsorption rate and beneficial to efficient treatment and real-time monitoring of iodine; the preparation method is simple in step, convenient to operate and low in equipment requirement.

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.

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 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 discloses a nuclear medicine radioactive waste liquid deep purification unit and an application method. The nuclear medicine radioactive waste liquid deep purification unit comprises a deep purification module constructed by n serial short ion exchange columns, the liquid collecting tank 1 and the liquid collecting tank II are respectively arranged at the front liquid inlet end and the rear liquid inlet end of the deep purification module; wherein the liquid inlets of all the short ion exchange columns are respectively connected with the liquid collecting tank 1, the liquid outlets of all the short ion exchange columns are respectively connected with the liquid collecting tank II, and the liquid inlets and the liquid outlets of all the short ion exchange columns are respectively connected with one another through valves; and the liquid outlets and the liquid inlets of the adjacent short ion exchange columns are connected through valves. According to the nuclear medicine radioactive waste liquid deep purification unit and the application method, the nuclear medicine radioactive waste liquid deep purification unit is designed on the basis of the short ion exchange column with the small height-diameter ratio, and disturbance of the purification capacity and waste of exchange fibers or resin caused by replacement of the ion exchange column can be reduced; meanwhile, the replaced new ion exchange column can be always positioned at the tail end, so that the purification efficiency is improved.

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 relates to the technical field of applicator, in particular to a radionuclide applicator and a preparation method thereof. Which comprises a shell on which a handle is arranged, and is characterized in that a source core is arranged in the shell, the source core sequentially comprises a first palladium layer, a first silver layer, an active layer, a second silver layer and a second palladium layer from inside to outside, and the active layer is a SrCO3-Ag layer; epoxy resin layers are arranged on the periphery of the source core and one side wall close to the handle. The radioactive substance of the active layer adopted by the radionuclide applicator provided by the invention is obtained by extracting, separating and purifying the radioactive waste liquid and has the characteristic of high purity, high-heat-release nuclides in the radioactive waste liquid are reduced, and the active layer is obtained by precipitating, filtering, calcining, pressing and rolling, so that the source core of the applicator has the characteristic of high uniformity.

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 technical management field of nuclear power plants, and particularly relates to a continuous exhaust system and method for a nuclear power plant voltage stabilizer, the system comprises an automatic pressure relief main pipeline, an exhaust pipeline, a first electromagnetic isolation valve, a second electromagnetic isolation valve, a throttling orifice plate, a drain tank, a radioactive waste gas system, a voltage stabilizer and a pressure stabilizing valve; an automatic pressure relief main pipeline and a pressure stabilizer safety valve are arranged at the top of the pressure stabilizer, an exhaust pipeline is arranged on the automatic pressure relief main pipeline, and the exhaust pipeline is connected with a radioactive waste gas system through a drain tank; a throttling orifice plate is arranged on the automatic pressure relief main pipeline and located on the upstream of the exhaust pipeline. A first electromagnetic isolation valve, a second electromagnetic isolation valve and a pressure stabilizing valve are sequentially arranged on the exhaust pipeline; and the pressure stabilizing valve is an automatic downstream pressure regulating valve. Continuous and stable exhaust of the voltage stabilizer can be achieved, the exhaust frequency is greatly reduced, and meanwhile the operation reliability of the electromagnetic isolation valve 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 invention discloses a compatibility system for treating radioactive waste and a treatment device and method, and relates to the technical field of radioactive waste treatment devices.The compatibility system comprises a temporary storage room, a database management system, a sorting system, a crushing system and a packaging system; the temporary storage room is used for carrying out physical property identification and radioactivity identification on the waste; the basic data recognized by the temporary storage room enters a database management system, and a first compatibility scheme conforming to the basic data is called out from a database; performing primary selection in a sorting system according to the first compatibility scheme; self-adaptive adjustment is carried out according to the working condition in the furnace, and a second compatibility scheme is formed; a third compatibility scheme is formed according to the working condition of the tail gas, so that the conventional pollutant emission of the system reaches the standard; self-adaptive adjustment is carried out according to the radioactive emission working condition, and a fourth compatibility scheme is formed; after the compatibility is completed, entering a crushing system; and feeding into a packaging system after crushing. The radioactive waste treatment efficiency is improved, and the system safety and radioactive risks are reduced.

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 reactor building radioactive waste liquid measuring device, a sampling measuring system and a method. The reactor building radioactive waste liquid measuring device comprises a measuring module, the measuring module comprises a measured liquid container, a first liquid level monitoring module and a radioactivity measurement and control module, the first liquid level monitoring module is arranged on the peripheral side of the measured liquid container, the radioactivity measurement and control module is arranged below the measured liquid container, and the first liquid level monitoring module is connected with the radioactivity measurement and control module. The measured liquid container is used for containing measured radioactive waste liquid, the first liquid level monitoring module is used for monitoring the liquid level in the measured liquid container, and the radioactivity measurement and control module is used for measuring the radioactivity concentration of the radioactive waste liquid; the first quantitative sample injection module is connected with the tested liquid container, and the first quantitative sample injection module is used for quantitatively injecting radioactive waste liquid into the tested liquid container. According to the technical scheme, measurement can be carried out without human intervention, and radiation safety of workers is guaranteed.

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 technical field of nuclear waste liquid transport vehicles, and discloses an intelligent transport vehicle for nuclear power plant radioactive waste liquid sampling and a control method.The transport vehicle comprises a chassis, a storage part arranged on the chassis and a mechanical arm used for grabbing a carrier containing nuclear waste liquid; the storage part is internally provided with a plurality of carrying positions for placing the carriers, each carrying position is internally provided with a weighing module and a positioning module, and the weighing modules and the positioning modules are electrically connected with the mechanical arm; the positioning module is used for detecting and positioning the position of the carrier placed on the carrying position and outputting positioning information; when the mechanical arm places the grabbed carrier on the carrying position, the mechanical arm adjusts the lowering position of the carrier according to the positioning information of the grabbed carrier by the positioning module, so that the lowering position of the carrier is matched with the position of the weighing module; therefore, the total weight of the carrier and the nuclear waste liquid contained in the carrier can be accurately obtained. The carrier is positioned and calibrated at the specific height, positioning and lowering of the carrier are guided, the collision risk of the carrier during lowering can be effectively avoided, and potential safety hazards are reduced.