539 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 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.

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

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 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.

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.

The invention relates to the technical field of radiation protection and environment monitoring, and particularly discloses a radioactive waste gas emission radiation dose real-time monitoring system which comprises a fixed monitoring base station network, an autonomous mobile monitoring cluster, a data fusion and cooperative control center and a radiation dose field three-dimensional reconstruction and evaluation terminal. Through air-ground cooperative monitoring, plume prediction and intelligent path planning based on an atmospheric diffusion model, and a physically constrained spatial interpolation algorithm, efficient tracking of a radioactive plume three-dimensional dynamic diffusion process and accurate reconstruction and visual evaluation of a three-dimensional dose field are realized. According to the system, an air-ground cooperative monitoring system composed of a fixed base station network and an autonomous mobile cluster is constructed, so that a passive and static monitoring normal form is fundamentally changed.

The invention provides a method for purifying strontium-90, which belongs to the technical field of separation and purification, and comprises the following steps: evaporating a strontium-90 aqueous solution extracted from high-level liquid waste, and adjusting the acid with fuming nitric acid to obtain a seasoning liquid; stirring the seasoning liquid, standing, filtering, washing the obtained precipitate, and dissolving to obtain a dissolved solution; loading the dissolving solution onto a pre-balanced strontium resin column, then sequentially eluting the strontium resin column by using a first eluting agent, a second eluting agent and a third eluting agent, and then eluting strontium-90 on the strontium resin column by using an eluent to obtain an eluent; loading the eluent onto an oil removal column, and collecting effluent, namely a purified strontium-90 solution. According to the method for purifying the strontium-90, equipment and operation are relatively simple, a non-radioactive carrier does not need to be added in the purification process, and the purification degree is relatively high.

The invention discloses a multi-stage leaching purification method of a targeted therapeutic drug. The multi-stage leaching purification method comprises the following steps: sequentially filling an adsorption column with a porous organic polymer layer and an adsorption ball layer; controlling the flow rate of the leacheate and the column temperature for leaching, and setting an adsorption saturation threshold value; carrier gas is adopted to heat and desorb the porous polymer layer, and carrier gas components are switched to heat and desorb the adsorption ball layer; the method comprises the following steps: introducing carrier gas carrying iodine vapor into an alkaline absorption tower to treat waste gas, eluting impurities of adsorption balls by adopting an acidic mixed solution, and performing catalytic degradation by combining ultraviolet light; a chelating agent solution is used for regenerating adsorption balls, a silver salt solution is used for heavily loading silver ions, an organic solvent is used for eluting and regenerating a porous polymer, regular calibration and part replacement are conducted on a system, and organic pollutants and radionuclides in a matrix are difficult to treat synchronously through a traditional single-layer adsorption material; according to the leaching purification method, the generation amount of radioactive waste liquid is remarkably reduced, and meanwhile the shielding protection requirement of the follow-up purification step is reduced.

The utility model relates to a dynamic measuring device for activity of medical radioactive waste liquid, in particular to the field of radiation monitoring, which comprises a sample chamber and a detector. The sample chamber is provided with a liquid level detection device, an overflow detection device, a sample feeding / discharging pump and cleaning equipment; the sample chamber comprises a protection cavity and a Marinin cup-shaped sample box; the detector is positioned above the Marinin cup-shaped sample box; the liquid level detection device comprises first liquid level detection equipment arranged at the bottom end of the sample chamber and movable second liquid level detection equipment; the overflow detection device is used for detecting whether materials in the sample chamber overflow the sample chamber; the medical radioactive waste liquid decay pool is connected with the sample chamber through the sample injection / discharge pump; and a control valve is arranged between the sample feeding / discharging pump and the sample chamber. The measuring device provided by the utility model can accurately measure the activity of radionuclides in the waste liquid, and can realize that the measuring result can be traced to the national social public measurement standard through accurate measurement, so that the reliability is guaranteed.

The invention relates to the field of metal corrosion behavior monitoring and characterization, in particular to a long-term corrosion test device and method for a high-level radioactive waste geological disposal packaging container material. The test device comprises an open container, a sealing material, a temperature-resistant plastic sealing tank, a buffer material, a temperature control component, a packaging container candidate material test sample, a wire and silicone rubber, the sealing material is arranged in the open container, the temperature-resistant plastic sealing tank is embedded in the sealing material, the buffer material is filled in the temperature-resistant plastic sealing tank, and the temperature control component is arranged in the temperature-resistant plastic sealing tank. A sensor for electrochemical impedance spectroscopy measurement, a corrosion weightlessness sample and a corrosion product characterization sample are embedded in the buffer material; the wire penetrates through a sealing tank top cover of the temperature-resistant plastic sealing tank, and the temperature control component is inserted into the sealing tank top cover of the temperature-resistant plastic sealing tank. The device is suitable for long-term corrosion research and evaluation of a packaging container candidate material in a high-level radioactive waste geological disposal buffer material environment, and has the characteristics of multiple functions, high operability, good sealing performance, high stability and real-time measurement.

The invention discloses a radioactive waste graphite incineration treatment and tail gas purification and sealing treatment process, and relates to the field of radioactive waste treatment. Flue gas generated by incineration treatment is cooled and purified; according to the present invention, the carbon dioxide in the cooled and purified flue gas is concentrated and compressed, and the compressed carbon dioxide is subjected to geological storage so as to achieve the permanent fixation of the 14C, such that the problem that the existing radioactive waste graphite consumes the excessive stock can be solved, the generated secondary radioactive waste is less, and the emission problem of the 14C is avoided through the utilization of the new process.

The present invention relates to the field of nuclear technology. A container for storing, transporting, and disposing of solid radioactive waste comprises a canister made of reaction-sintered silicon carbide with a free silicon content of 3% to 30% by weight, with a fumed silicon carbide layer deposited on the canister's surface. The canister's outer layer is made of metal foam with an open porosity of 60% to 70% and a pore size of 5 mm to 6 mm. The pores are filled with dispersed boron carbide powder of 40 to 50 μm in diameter, thereby protecting the environment from nuclear radiation emitted by high-level radioactive waste. A stainless steel cylinder with a thickness of 1 mm to 1.5 mm, intended to contain radioactive waste, is placed within the silicon carbide canister. A 5 mm gap between the inner surface of the silicon carbide canister and the stainless steel cylinder is filled with boron carbide powder, thereby protecting the environment from nuclear radiation emitted by high-level radioactive waste. The silicon carbide canister is sealed with a lid made of silicon carbide using a reaction welding method. The metal foam used as the metal foam with an open porosity is selected from the group consisting of titanium, aluminum, and copper. The present invention can increase the strength of containers for solid radioactive waste.

The utility model discloses a radioactive waste storage cabinet which comprises a bottom plate, a surrounding plate and a front baffle are installed on the upper surface of the bottom plate, and the front baffle is located on one side of the surrounding plate. A radioactive waste storage barrel and a moving assembly used for moving the radioactive waste storage barrel are arranged in a storage cavity formed among the bottom plate, the surrounding plate and the front baffle, a moving plate is arranged on the moving assembly, and a connecting plate is installed at the rear end of the upper surface of the moving plate. An electric push rod used for pushing the moving plate to move is installed on the outer wall of one side of the connecting plate, and the other end of the electric push rod is installed on the inner wall of one side of the surrounding plate. According to the radioactive waste storage device, a worker can conveniently move the radioactive waste storage barrel out of the storage cavity or place the radioactive waste storage barrel into the storage cavity, the moving height of the radioactive waste storage barrel when the worker moves out of the radioactive waste storage barrel is reduced, the labor intensity of the worker is reduced, and time and labor are saved.

This invention discloses a method for precipitation separation and ceramic solidification of divalent strontium and tetravalent uranium in radioactive waste liquid, relating to the field of radioactive waste liquid treatment and disposal. U in high-level radioactive waste liquid is in the form of hexavalent uranyl (UO2). 2+ U exists in the form of hydrogenation catalytic reduction, and the present invention uses hydrogenation catalytic reduction to prepare U. 4+ Sr 2+ and U 4+ ionic radius and Ln 3+ Due to the significant differences, CePO4·0.667H2O cerium phosphate, which has a stronger nuclide-containing capacity, was selected as the co-precipitation enrichment agent for Sr. 2+ and U 4+ Separation precipitant. Inexpensive raw materials such as UO2(NO3)2·6H2O, Sr(C2H3O2)2, NH4H2PO4, and Ce(NO3)3·6H2O are selected. By controlling the Sr... 2+ :U 4+ Ion ratio, reaction time, temperature, pH, and preparation of well-developed Sr crystals 2+ / U 4+ The precipitate of cerium phosphate solid solution with high solid content is avoided by using spark plasma solid-state sintering technology to prevent grain agglomeration and adhesion during high-temperature dehydration and crystal transformation of cerium phosphate. Furthermore, pressure sintering can promote further growth of nanocrystals and promote U... 4+ and Sr 2+ Homogenization within the monazite ceramic solidified body enables a one-step preparation of monazite ceramic solidified body from a lanthanite solid solution.

The utility model discloses a nuclear power plant radioactive waste barrel gamma scanning device and measuring equipment, and the nuclear power plant radioactive waste barrel gamma scanning device comprises a supporting seat, a sealing cover, a rotating disc, a control mechanism and a fixing assembly. The sealing cover is detachably mounted on the supporting seat, and a sealing cavity is formed between the sealing cover and the supporting seat; the turntable is detachably mounted on the supporting seat and rotates in the sealing cavity; the fixing assembly is installed on the rotating disc, the radioactive waste barrel is detachably fixed to the rotating disc, and the axis of the radioactive waste barrel is parallel to the plane of the rotating disc. Therefore, the total activity of the radioactive raw material in the radioactive waste barrel can be quickly obtained only through twice measurement, the measurement efficiency and the accuracy of activity reconstruction are improved, the layering frequency is reduced, and the measurement time is saved.

The utility model discloses a transport container for radioactive waste barrels, which comprises a top cover, a barrel body and a base, the barrel body is mounted above the base, the top cover is mounted above the barrel body, the top cover is used for sealing the barrel body, and the radioactive waste barrels are placed in the barrel body. The top cover comprises a cover body and a lifting part above the cover body, the lifting part is used for lifting the top cover, and a plurality of long slotted holes are formed in the cover body; the barrel body comprises a barrel body, a barrel body flange plate, a positioning rib plate, a wrap angle and a plurality of lifting lugs, the barrel body flange plate is fixed at the top end of the barrel body, the barrel body flange plate and the cover body are connected at any angle through a long slotted hole by using a bolt, the positioning rib plate is arranged at the lower end of the inner side wall of the barrel body, the wrap angle is arranged on the outer side of the barrel body flange plate, and the lifting lugs are fixed on the outer side of the barrel body; the base comprises a base plate and a plurality of forklift grooves, and the forklift grooves are fixed below the base plate. The transportation container is safe, stable, easy to load and transport, shockproof and capable of being integrally transferred.