454 results about "Radioactive agent" patented technology

The invention discloses a radioactive substance multi-point synchronous detection and identification method and system, and relates to the technical field of radioactive substance monitoring. Comprising the following steps: step 1, collecting multi-point radiation data in real time, and preprocessing and storing the data; step 2, constructing a spatial adjacency matrix, estimating a local spatial gradient, calculating an anomaly degree value, taking optimization measures, and performing collaborative anomaly evaluation on the monitoring nodes; 3, calculating a total fitting error value, reversely deducing a leakage source position and leakage intensity in real time, and taking corresponding measures in real time; 4, abnormal trend identification is carried out, an early warning judgment value is calculated, and graded early warning and multi-node cross confirmation measures are implemented; and 5, receiving and storing various types of data, carrying out visualized analysis on the data, and supporting event processing and feedback. The problems that due to the fact that some devices are good in shielding and have physical obstruction, trace leakage is difficult to detect by a single-point monitor, and the risk of long-term retention pollution exists are solved.

The invention provides an intelligent sorting method and system for radioactive substances. The method comprises the following steps: synchronously detecting surface element composition and radiation intensity of a radioactive substance through an X-ray fluorescence spectrometer, and constructing a spatial difference matrix of element abundance distribution and a radiation gradient topological graph; the three-dimensional coordinates, the pressure threshold value and the shape adaptation parameters of the target grabbing position are determined on the basis, the curvature radius of the clamping jaw deformation contour is dynamically adjusted, and the error of the dynamic geometric envelope and the contour template is converged to be within the threshold value; finally, when the clamping jaw reaches a target position, the area of the heat shrinkage material is activated to be heated according to the radiation intensity abrupt change boundary coordinates, a sealed isolation layer synchronously expanded with the dynamic geometric envelope is generated, and safe grabbing and sealed isolation of radioactive substances are achieved. According to the technical scheme, accurate grabbing of radioactive substances, error self-adaptive compensation and synchronous isolation of radiation leakage can be achieved, and the sorting safety and efficiency are improved.

The invention relates to a containment pressure suppression, filtration and discharge system and method and application thereof, and belongs to the field of special safety facilities and radiation protection of nuclear power devices. The containment pressure suppression, filtration and discharge system comprises a discharge valve (2), a discharge pipeline (3), a spray pipe (4), a pressure suppression pool, an expansion chamber (7), a steam-water separator (9), a metal fiber filter layer (10), a rupture disk (12), a heat exchanger and a valve. According to the containment pressure suppression filtering and discharging system, the seawater side heat exchanger and the pressure suppression pool heat exchanger are arranged, and a natural circulation loop is constructed by means of the potential difference between the seawater side heat exchanger and the pressure suppression pool heat exchanger and the temperature difference between seawater and a liquid phase in a pressure suppression pool under the accident condition; the heat of the suppression pool can be guided out without time limit under the condition of an LOCA accident or a main steam pipeline fracture accident in the containment; by adopting a pressure suppression washing method with multi-stage bubbling, rapid pressure suppression of the containment and efficient retention of airborne radioactive substances can be realized; occupation of total resources is reduced by arranging the combined metal fiber filter layer.

The invention relates to the technical field of brazing processes, in particular to a brazing process for connecting aluminum oxide ceramic and metallic titanium through low-activation brazing filler metal. According to the technical scheme, the method comprises the following steps that a to-be-welded face of the aluminum oxide ceramic is subjected to magnetron sputtering titanium film plating, the sputtering power ranges from 80 W to 150 W, the argon pressure ranges from 0.5 Pa to 1.5 Pa, the film thickness ranges from 0.5 micrometer to 5 micrometers, inert gas annealing treatment is conducted after film plating, the annealing temperature ranges from 400 DEG C to 550 DEG C, and the heat preservation time ranges from 10 min to 30 min; and the surface of the metal titanium substrate is subjected to laser micro-texture treatment, and a periodic groove structure with the depth being 10-50 microns is formed. The problems of poor wettability of the brazing filler metal and the ceramic, low joint strength and joint stress cracks are solved, meanwhile, radioactive substances generated by the brazing filler metal under the irradiation condition can be released within a short time, the equipment maintenance period is greatly shortened, and the equipment service life is prolonged.

The invention discloses a nuclear leakage radioactive substance diffusion situation inversion method and device, and relates to the technical field of nuclear emergency response. The method comprises the following steps: acquiring initial source item parameters and meteorological data, and obtaining a nuclide concentration predicted value through a Gaussian puff model according to the initial source item parameters and the meteorological data; acquiring a nuclide concentration observation value corresponding to the nuclear leakage area, and performing Kalman filtering fusion processing according to the nuclide concentration prediction value and the nuclide concentration observation value to obtain a nuclide optimal concentration field and analysis error distribution; adjusting parameters of a Gaussian diffusion mode according to the analysis error distribution to obtain an adjusted Gaussian diffusion mode, and obtaining target source item parameters based on the adjusted Gaussian diffusion mode and the optimal concentration field; and performing iteration by taking the target source item parameter as an initial source item parameter until a preset requirement is met, and taking the source item parameter obtained when iteration is ended as a final source item parameter. The method can dynamically respond to the sudden change of atmospheric stability, and improves the prediction precision of the nuclear hazard area range.

Interstitial brachytherapy is a cancer treatment in which radioactive material is placed directly in the target tissue of the affected site using an afterloader. The accuracy of this placement is monitored in real time using a urinary catheter that locates the radioactive material according to the radiation levels measured by sensors in the walls of the urinary catheter. A scintillator that is embedded in the walls of the urinary catheter produces light when irradiated by the radioactive material. This light is proportional to the level of radiation at each location. The light produced by each scintillator is carried through optical fibers and then converted to an electrical signal that is proportional to the light and the radiation level at each location. The radioactive material is located according to the plurality of electrical signals. This location can be used as quality control feedback to the afterloader.

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 provides an online monitoring device for multiple nuclides in liquid effluent, and particularly relates to the technical field of radioactive substance detection. The online monitoring device comprises a shell, a cascade separation module, a fluid control module, a detection module and a control system, the cascade separation module, the detection module and the control system are arranged in the shell, the cascade separation module comprises a plurality of resin columns and a plurality of separated liquid collecting bottles communicated with the resin columns, and the separated liquid collecting bottles are communicated with the resin columns. The fluid control module comprises a liquid storage device, an injection pump and a control valve, the liquid storage device is respectively communicated with the plurality of resin columns through pipelines, the injection pump and the control valve are respectively arranged on the pipelines and are used for controlling the flow direction and the flow velocity of fluid in the liquid storage device, and the detection module is used for detecting the radioactive activity of nuclide; the control system is used for controlling operation of the cascade separation module, the fluid control module and the detection module. According to the invention, synchronous monitoring of multiple nuclides is realized, the multi-nuclide monitoring efficiency is improved, and the monitoring cost is reduced.

The embodiment of the invention provides an assessment method and device for nuclear power off-site radioactive substance release influence, and belongs to the technical field of nuclear power. The method comprises the following steps: acquiring an evaluation range for evaluating the release influence of radioactive substances, wherein the radioactive substances are released in a smoke plume form; within a preset evaluation duration, simulating the generation and movement process of the smoke plume within the evaluation range according to the meteorological condition of the release site, and obtaining the accumulated concentration and settlement concentration of the smoke plume; calculating according to the accumulated concentration and the settlement concentration to obtain the dose of air immersion external irradiation, the dose of surface external irradiation and the dose of suction internal irradiation in the evaluation range; and performing radiation evaluation according to the dose of the air immersion external irradiation, the dose of the surface external irradiation and the dose of the suction internal irradiation to obtain an evaluation result. According to the embodiment of the invention, migration, settlement, diffusion and other phenomena of the radioactive smoke plume in different areas outside the field can be tracked, influences of meteorological condition changes and settlement are coupled, and the accuracy of an evaluation result 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 relates to the technical field of modeling, in particular to a multi-mode imaging and three-dimensional laser scanning fused radioactive distribution modeling method. The method comprises the following steps: performing multi-angle detection on target three-dimensional space radioactive substances based on radioactive detection equipment to obtain a radioactive substance distribution two-dimensional image set; based on a laser scanning device, collecting three-dimensional point cloud data of a target three-dimensional space, assembling the three-dimensional point cloud data, and constructing a target three-dimensional space 3D model; based on the radioactive substance distribution two-dimensional image set, reducing a distribution image of the radioactive substance in the target three-dimensional space by adopting a statistical reconstruction algorithm; and based on the target three-dimensional space 3D model and the distribution image, combining to obtain a radioactive substance three-dimensional distribution modeling result. The technical effect of visually and accurately displaying the distribution condition of the radioactive substances in the three-dimensional space is achieved.

The invention provides a multi-nuclide automatic separation and detection system and method, and particularly relates to the technical field of radioactive substance detection. The detection system comprises a cascade separation and regeneration unit, a dynamic regulation and control unit, an online detection unit, an eluent conveying unit and a control system, and the eluent conveying unit is matched with the cascade separation and regeneration unit to separate and purify radionuclide and regenerate resin. The dynamic regulation and control unit is used for controlling a flow path between the eluent conveying unit and the cascade separation regeneration unit and feeding back changes of pressure, temperature and pH value in the flow path in real time, and the online detection unit is used for detecting concentration of nuclides in separation liquid and feeding back monitoring data to the control system. And the control system controls the operation of each functional unit and automatically plans a separation path according to a measurement requirement to form a separation-detection-optimization closed-loop process. The device is suitable for the fields of nuclear facility liquid effluent detection, environmental water radioactivity detection and the like, and has high efficiency, environmental protection property and intelligence.

The invention discloses a multi-layer steel lining containment structure, and the containment comprises an inner layer steel lining which is in contact with gas in the containment and is used for encapsulating radioactive substances; the outer-layer steel lining and the inner-layer steel lining form an interlayer, and the interlayer is provided with a filling space; the concrete shell is arranged on the outer layer of the outer-layer steel lining so as to protect the outer layer of the outer-layer steel lining; the filling space is filled with the phase change material, and the phase change performance of the phase change material can realize defect self-repairing of the containment. According to the structure, multiple functions of passive impact buffering, pressure balancing, rapid heat guiding-out, defect repairing and the like can be integrated.

The invention provides a method, a device and equipment for determining a decontamination path of a radioactive substance contaminated metal plate, and relates to the technical field of nuclear facility decommissioning governance, and the method comprises the steps: obtaining a metal plate image; dividing the metal plate image into a plurality of detection areas; radioactive substance pollution detection is carried out on the multiple detection areas, and area pollution values are determined; determining a polluted area according to the area pollution value; and determining a decontamination path of the radioactive substance polluted metal plate according to the polluted area. According to the scheme, the decontamination sequence and the decontamination times of all the detection subareas are designed, the decontamination track is planned, pertinence is better achieved, the pollution level of the plate metal can be rapidly reduced, and the decontamination efficiency is effectively 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 container dismantling device which improves workability of container dismantling work.SOLUTION: A container dismantling device for dismantling a container contaminated with radioactive substances is provided, the device comprising a base supported at the bottom inside the container, a support member disposed along a vertical direction and supported by the base at a bottom thereof, and a cutting device supported by the support member in such a way that the cutting device is movable along the vertical direction and movable in the circumferential direction.SELECTED DRAWING: Figure 2

The invention discloses a diabase tailing geopolymer cementing material and a preparation method thereof, and belongs to the technical field of building materials. The diabase tailing geopolymer cementing material provided by the invention is prepared from the following components in parts by mass: 80 to 120 parts of diabase tailings, 10 to 20 parts of sodium hydroxide, 80 to 120 parts of water glass, 10 to 20 parts of aluminum hydroxide, 1 to 3 parts of a water reducing agent and 2 to 11 parts of a stabilizing material, the geopolymer cementing material is prepared from the solid waste diabase tailings, harmful solvents, heavy metals and radioactive substances are not added, waste can be turned into wealth, the preparation process is simple, the cost is low, the energy consumption is small, and an effective way is provided for comprehensive utilization of the diabase tailings.

Disclosed in the present invention is a fuel rod for a water-cooled reactor. The fuel rod comprises a cladding tube, an upper end plug and a lower end plug that match at two opposite ends of the cladding tube, and fuel pellets stacked in the cladding tube, wherein the fuel pellets comprise at least one first pellet; the first pellet is formed by at least two pellet units connected in an enclosed manner in a circumferential direction; and a through hole penetrating two opposite ends of the first pellet is formed in the first pellet, and is filled with a filler containing burnable poison nuclides. In the fuel rod for a water-cooled reactor of the present invention, by means of providing a hole in a pellet and filling the hole with the filler containing the burnable poison nuclides, a gas generated by the pellet during the operation of the reactor can be absorbed, thereby reducing the internal pressure of the cladding tube, reducing the risk of fuel rod failure, preventing the leakage of radioactive substances, increasing the uranium utilization rate, and providing a relatively large design margin.

To provide a method for recovering a drying operation in drying of an adsorbent in an adsorption tower capable of preventing movement of the adsorbent downstream during restoration of a drying operation after stop of drying the adsorption tower and thereby enhancing safety.SOLUTION: A method for recovering a drying operation, in which a vacuum pump 13 is connected downstream of an adsorption tower 10 via piping to reduce pressure inside the adsorption tower 10 by sucking air containing water vapor W1, for restoring, upon stop of a drying operation for drying an adsorbent in an adsorption tower 10 that adsorbs radioactive substances contained in contaminated water, includes: restarting the vacuum pump 13 so that the internal pressure of the adsorption tower becomes a set degree of vacuum on the basis of an operating condition under which the adsorbent inside the adsorption tower 10 does not flow; and the vacuum pump 13 operating for a running time of 45 minutes or more and 60 minutes or less from the start of the restart so that the internal pressure of the adsorption tower becomes 2.4 kPa.SELECTED DRAWING: Figure 1

The invention relates to a mobile source nuclear accident consequence evaluation method and system, computing equipment and a storage medium. The method comprises the following steps: acquiring geographic data and meteorological data; calculating a meteorological field according to the geographic data and the meteorological data, generating meteorological field data, and obtaining source item data of the moving source according to a plurality of point sources of the moving source on the moving path; diffusion calculation of the moving source is carried out according to the source item data and the meteorological field data, and concentration field data of the moving source is generated; and performing dose calculation according to the concentration field data to generate dose field data of the mobile source. According to the technical scheme provided by the invention, the radioactive substance diffusion process of the mobile source can be effectively evaluated.

The invention belongs to the technical field of elemental analysis, and provides a spent fuel sample total alpha and total beta activity analysis system and a spent fuel sample total alpha and total beta activity transportation and analysis method.The system comprises a glove box and an analysis unit, and a shielding chamber and a conveying assembly are installed in the glove box; a detector assembly is mounted in the shielding chamber and is used for detecting a sample in the shielding chamber; the conveying assembly is used for conveying samples, and the samples are placed in the tray; the analysis unit is located outside the glove box, connected with the detector and used for analyzing data detected by the detector. According to the analysis system, split design of the glove box and the analysis unit is adopted, the part in contact with the sample is placed in the glove box, the radioactive process sample can be analyzed and detected, the risk of radioactive substance leakage is reduced, meanwhile, the analysis unit is placed outside the glove box, radiation of the radioactive substance is avoided, the service life is prolonged, and the cost is reduced. And the maintenance operation is also convenient.

The invention relates to the technical field of constructional engineering water supply and drainage treatment, and discloses a constructional engineering water supply and drainage filtering method which comprises the following steps that a pretreatment box and a filtering box are utilized, and a movable shaft and a collecting box are arranged in the pretreatment box and used for preliminarily filtering impurities; sewage is settled through the cyclone grit chamber in cooperation with combined placement of coarse corrugated plates, fine corrugated plates, coarse fiber balls, fine fiber balls, anthracite and activated carbon, the blocking and cleaning frequency in the settling and filtering process is reduced, the use amount of chemicals in the whole sewage treatment process is reduced, the labor intensity of operators is reduced, and the sewage treatment efficiency is improved. Through biological filtration, peculiar smell, color, suspended matters and various pollutants such as heavy metal ions and radioactive substances in water are effectively removed, the water is remarkably improved, through metabolic activity of microorganisms, organic matters including substances difficult to degrade in the water can be degraded through biological filtration, the concentration of the pollutants is reduced, and environmental protection is facilitated.

The invention provides a test method and equipment for characterizing etching sediment distribution, and the method comprises the steps: arranging a sampling cabin on the side wall of an etching chamber, and placing a sampling piece in the sampling cabin; introducing radioactive isotope labeled etching gas to carry out an etching process; and performing radioisotope imaging analysis on the sampling piece to obtain distribution data of the etching sediment. The radioactive isotope labeled sediments are collected through the sampling piece to obtain the distribution of the sediments in the etching chamber, so that the adjustment precision of etching process parameters is improved, and the device yield is improved; meanwhile, the representativeness of sediment distribution data is improved through the position distribution of the sampling bins; in addition, a sampling piece is placed in the sampling bin, so that the sampling piece effectively reflects the actual distribution condition of sediments on the side wall of the etching chamber, and meanwhile, operation and maintenance are convenient; finally, after the sampling piece is taken out, dry ice cleaning and radioactive substance detection are carried out in the etching chamber, and the influence of radioactive substance residues on the sediment distribution detection accuracy in the future and the damage to the etching chamber are avoided.

The invention provides a three-dimensional lithium battery mine visualization system based on digital twinning, and the system comprises a physical sensing layer which is disposed at a lithium battery mine site, and comprises a plurality of sensor networks used for collecting geologic bodies, production equipment, environment parameters, personnel positions, and vehicle states; and the data interaction layer comprises a data integration platform and an edge computing node, and is used for carrying out cleaning, fusion, protocol conversion and edge side preliminary analysis on the multi-source heterogeneous data uploaded by the physical sensing layer, and uploading the multi-source heterogeneous data to a cloud. By integrating the slope monitoring sensor and the professional analysis model, real-time evaluation and advanced early warning of the slope stability and the tailing pond safety are achieved, major accidents such as collapse and dam break are effectively prevented, meanwhile, the harmful element diffusion model is utilized, and the safety of the tailing pond is improved. Migration paths of fluoride dust, radioactive substances and potential leakage pollutants in the atmosphere and the water system are dynamically simulated, accurate decision support is provided for environmental risk emergency response, and the influence on surrounding ecology is reduced to the maximum extent.

The invention provides a method for synthesizing sodalite from 4A zeolite and synchronously solidifying radioactive waste salt in situ, and belongs to the technical field of radioactive waste salt solidification treatment of spent fuel dry post-treatment. The preparation method comprises the following steps: mixing 4A zeolite powder, radioactive waste salt, alkali metal chloride salt and a dispersing agent according to a certain liquid-solid ratio, heating, and drying to obtain a cured precursor; and grinding and sieving the cured precursor, and sintering under the condition of not exceeding 900 DEG C to obtain the sodalite cured body. The method provided by the invention is low in energy consumption, simple in process operation, small in 4A zeolite dosage, high in radioactive waste salt coating rate and high in radioactive element fixing amount; the synthesized sodalite solidified body is high in thermal stability and mechanical hardness, the normalized leaching rate after the sodalite solidified body is soaked in water at 90 DEG C for 28 days is smaller than 5 * 10 <-4 > g / (cm < 2 >. D), and the sodalite solidified body can be geologically stored for a long time, so that the migration, diffusion and leakage risks of radioactive substances are effectively reduced.

An automatic doctor blade (1) for scraping a radioactive target (101) to be used for a radiopharmaceutical, the automatic doctor blade comprising: a target holder (2) for holding a radioactive target; a scraping unit (3) comprising a scraping member for scraping the radioactive target located in the target holder; a receiver (5) for receiving material scraped from the radioactive target; a motor (6) for moving the scraping unit and the target holder relative to each other; and a control unit for controlling the motor. A surface (102) of the radioactive target to be scraped is arranged at an angle between 45 degrees and 315 degrees, the angle of 0 degrees corresponding to the radioactive target being oriented such that the surface of the radioactive target to be scraped is perpendicular to the vertical direction and facing upward, the angle of the target corresponding to a clockwise rotation of the target from 0 degrees.

Disclosed is a system and a method enabling the behavior of a radioactive substance within a structure to be determined. More particularly, the disclosed is a system and a method wherein it is possible to determine, along a column, the position and / or distribution and / or movement speed of the substances moving within the column and / or the time when the substances will leave the column and how much of the substance reaching the column outlet will begin to leave the column and with what activity, and consequently, it is possible to provide optimization and automation for proceeding to the next process step.

The invention relates to the technical scheme. The invention belongs to the field of new energy and nuclear energy battery technology. The method is a comprehensive and systematic method for directly converting radioactive substances and radiation of the radioactive substances into electric energy. The utilization of radioactive substances is the utilization of a contact potential effect existing among substances with different Fermi levels. The utilization of the radiation is the utilization of the contact potential effect of a non-Fermi level; according to the technical scheme, the contact potential effect formed by the electric potential generated by radiation rays and radiation on a polar plate is utilized, and the effect is converted into electric energy capable of being actually utilized under the action of a medium which has conductivity and controls voltage and limits conductivity under a certain condition.

The invention is suitable for the technical field of radiation detection and radioactive substance monitoring, and provides an intelligent offshore buoy which comprises an intelligent buoy body, the intelligent buoy body is used for monitoring the concentration of radioactive substances on the sea, and the intelligent buoy body comprises a buoy body, the system comprises a buoy body, an instrument cabin, a data acquisition and transmission control terminal module, a battery, a Na I detector, a Beidou, a data transmission antenna, a G-M tube detector and a solar panel, and the instrument cabin is fixedly installed in the buoy body. According to the offshore intelligent buoy provided by the scheme, the concentration of radioactive substances on the sea can be well monitored, dust adhered to a plurality of solar panels can be conveniently cleaned, the conditions of corrosion and shading of the solar panels caused by the dust are reduced, the power generation efficiency of the solar panels is effectively improved, the service life of the solar panels is effectively prolonged, and the service life of the solar panels is prolonged. Therefore, the overall use stability is effectively guaranteed, and the stability of monitoring the concentration of the radioactive substances on the sea is further guaranteed.

The embodiment of the invention relates to the technical field of radioactive substance transfer, in particular to a radioactive substance dissolving system and a complexing device thereof. The device is used for complexing fluorine ions in a dissolving solution in which radioactive substances are dissolved by using an aluminum ion complexing agent, and comprises an annular accommodating part and a neutron absorbing part, wherein the annular accommodating part is arranged to form an annular accommodating cavity for accommodating a dissolving solution and an aluminum ion complexing agent; the neutron absorption part is arranged on the radial inner side of the annular containing part and used for absorbing neutrons. According to the device provided by the embodiment of the invention, the accommodating cavity for accommodating the dissolving solution and the aluminum ion complexing agent is arranged as the annular accommodating cavity, so that the capacity is improved on the premise of avoiding critical problems in the complexing process; the device provided by the embodiment of the invention is provided with the neutron absorber to absorb neutrons, so that the neutrons emitted by the radioactive substance in the annular accommodating cavity can be prevented from entering the annular accommodating cavity after being emitted out of the annular accommodating cavity and being absorbed by the fissile material to cause a critical problem.