542 results about "Nuclide" patented technology

The invention belongs to the field of medical radioactive isotope preparation, and particularly relates to a method for extracting lead-212 and bismuth-212 from a thorium-232 decay chain, a solution containing a thorium-232 decay chain substance passes through an anion exchange resin column, the solution containing the thorium-232 decay chain substance contains halide ions, and the anion exchange resin column is used for extracting the lead-212 and the bismuth-212 from the thorium-232 decay chain substance. The concentration of hydrogen ions in the solution containing the thorium-232 decay chain substance is greater than 0.01 mol / L, the lead-212 and the bismuth-212 are adsorbed by the anion exchange resin column, other nuclides directly penetrate through the anion exchange resin column and are not adsorbed, a leaching reagent is introduced to desorb the lead-212 and the bismuth-212 from the anion exchange resin column, and the lead-212 and the bismuth-212 are separated and extracted; the method can be used for simultaneously extracting lead-212 and bismuth-212, has the advantages of high extraction speed and high purity, and is not easy to cause organic pollution to products.

The invention relates to the technical field of unmanned aerial vehicle-mounted nuclear radiation detection, and provides an unmanned aerial vehicle-mounted nuclear radiation detection method and system based on deep learning, and the method comprises the steps: collecting a gamma energy spectrum signal, and carrying out the digitization of the gamma energy spectrum signal, and obtaining original energy spectrum data; preprocessing the original energy spectrum data to obtain preprocessed energy spectrum data; constructing a nuclide identification model based on a deep learning network, and performing nuclide identification on the preprocessed energy spectrum data to obtain an original nuclide identification result; performing post-processing analysis and refinement on the original nuclide identification result to obtain a nuclide identification result; and fusing the nuclide identification result with the geographic position information to obtain a nuclear radiation pollution distribution diagram, and setting a multi-level early warning mechanism based on nuclide types and intensity. According to the invention, the precision of nuclide identification in a complex environment is improved, and high-sensitivity detection of various nuclides under the condition of low signal-to-noise ratio is realized.

The invention provides a solid target system for simultaneously producing Ge-68 and PET nuclides under a high-power beam, and the system comprises an intermediate-energy cyclotron which is used for transmitting an intermediate-energy high-intensity proton beam; the cascade target is arranged beside the intermediate-energy cyclotron and comprises a shell, and a first aluminum target body, a second aluminum target body, a Ga4Ni alloy capsule target and a metal sealing target which are sequentially arranged along the emission direction of the intermediate-energy high-current proton beam, and the shell is filled with cooling water; the target film is erected between the intermediate energy cyclotron and the first aluminum target body; the helium cooling unit is erected between the target film and the first aluminum target body; and the control unit is used for controlling to start the helium cooling unit and the medium-energy cyclotron, so that the medium-energy high-intensity proton beam sequentially passes through the target film, the first aluminum target body, the shell and the cooling water, then enters the Ga4Ni alloy capsule target to produce Ge-68 nuclide, and then enters the metal sealing target to produce PET nuclide. The method has the beneficial effects that the melting of the target material can be reduced, the probability of direct chemical reaction of molten Ga and Nb is reduced, and the types of nuclide production are increased.

The invention belongs to the technical field of nuclear radiation measurement, and relates to a liquid flash TDCR multi-nuclide beta spectrum analysis method and system based on artificial intelligence. The method comprises the following steps: constructing a numerical model of a liquid flash detector spectrometer by using a Monte Carlo technology to simulate the energy spectrum response of a single nuclide under different quenching conditions; constructing a training database by adopting a parameterized data synthesis algorithm; constructing a multi-task mixed spectrum analysis neural network model; carrying out model training by utilizing the constructed database; and inputting an actual measurement spectrogram, and outputting the multi-nuclide absolute activity, the detector efficiency and the decomposition energy spectrum contribution curve in real time by using the trained neural network model. According to the method, differential distribution characteristics and quenching response curve characteristics of the beta continuous energy spectrum are creatively fused, a neural network architecture with physical mechanism constraints is constructed, and liquid flash TDCR multi-nuclide energy spectrum characteristic decoupling and accurate activity solving are achieved under the unknown quenching condition.

The invention provides a method for predicting the effective diffusion coefficient of nuclides in bentonite. The method comprises the steps of obtaining a data set; the data set comprises the pH value of underground water; and constructing a nuclide effective diffusion coefficient model by using the data set, and predicting the effective diffusion coefficient of a certain radioactive element in bentonite by using the constructed nuclide effective diffusion coefficient model. According to the method provided by the invention, the prediction precision of the effective diffusion coefficient of the nuclide can be effectively improved.

The invention provides an ore grade analysis method. The ore grade analysis method comprises the following steps: generating an X-ray beam by utilizing a radiation source; x-ray beams are utilized to irradiate the ore, target element nuclides in the ore are excited to generate a nuclear resonance fluorescence effect, target characteristic gamma rays are emitted, and the energy of the X-ray beams is higher than the excitation energy of the target element nuclides; when the X-ray beam is utilized to irradiate the ore, a standard sample containing a reference nuclide is irradiated, the reference nuclide is excited to emit a reference characteristic gamma ray, and the reference nuclide is expressed as a nuclide with known content and known characteristic gamma ray energy; detecting the energy of a target characteristic gamma ray and the energy of a reference characteristic gamma ray; and determining the grade of the target element in the ore based on the energy of the target characteristic gamma ray and the energy of the reference characteristic gamma ray.

The invention relates to the technical field of nuclear radiation monitoring, in particular to a water body total radioactivity and nuclide on-line measurement system which comprises a gamma detector, a beta detector, an alpha detector and a water treatment component, the water treatment component extracts a water body sample and processes the water body sample, and then the water body sample passes through the gamma detector, the beta detector and the alpha detector; the gamma detector is arranged in a first shielding body, and the beta detector and the alpha detector are arranged in a second shielding body; the water treatment assembly provided by the invention is responsible for extracting and treating a water body sample, so that the water body sample sequentially passes through various detectors and a gamma detector to obtain a gamma energy spectrum of the water body sample, and a beta detector and an alpha detector respectively obtain beta and alpha total activity of the water body sample, and accurate detection of different types of radiation is realized.

The embodiment of the invention relates to the technical field of nuclear detection and measurement, and discloses a double-label nuclide analysis method and device and a program product, and the method comprises the steps: measuring a standard quenching source, and obtaining an external standard source spectrum index of the standard quenching source; drawing a correction curve by taking the external standard source spectrum index as an independent variable; measuring the double-labeled sample under external gamma source high voltage, and obtaining and calculating an external standard source spectrum index of the double-labeled sample through external gamma source spectrum stripping; determining the counting efficiency of low-energy nuclide, the counting efficiency of high-energy nuclide, the spectrum index of the low-energy nuclide sample and the spectrum index value of the high-energy nuclide sample corresponding to the double-labeled sample under the current quenching level according to the external standard source spectrum index of the double-labeled sample and the correction curve; the method comprises the following steps: measuring a double-labeled sample under double-labeled high pressure to obtain a full-spectrum counting rate and a full-spectrum sample spectrum index of the double-labeled sample; the low-energy nuclide activity and the high-energy nuclide activity of the double-labeled sample are calculated based on the parameters, so that the operability is higher, the accuracy is higher, and the application range is wider.

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.

The invention discloses a method and a system for forecasting a radionuclide ocean transportation diffusion path, and the method and the system are used for updating a nuclear pollution area in combination with the diffusion of ocean radionuclides, and determining the atmospheric environment information of a nuclear pollution sea area from an atmospheric environment information forecasting system; selecting hydrodynamic element information from a plurality of marine environment information forecasting systems in combination with the spatial resolution and the regional range of each marine environment information forecasting system; and thus, optimal ocean water power driving information and sea surface driving information are established to carry out diffusion path forecasting. Meanwhile, according to the method, based on the types of radionuclides, a corresponding model is selected to forecast the marine transportation diffusion path of the radionuclides, and for the radionuclides which are easily adsorbed to suspended solids, the marine transportation diffusion path of the radionuclides is predicted by combining adsorption and sedimentation driving information of the suspended solids to the radionuclides while diffusion path analysis is carried out. And the prediction accuracy of the radionuclide ocean transport diffusion path can be improved.

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

The invention provides a signal processing method for radioactivity detection equipment and the radioactivity detection equipment, and the signal processing method for the radioactivity detection equipment comprises the steps: analyzing a collected nuclear pulse signal, and obtaining pulse amplitude information; performing spectrum stabilization according to the pulse amplitude information to obtain a spectrum-stabilized energy spectrum; and determining a nuclide identification result and a dose rate calculation result based on the spectrum-stabilized energy spectrum. According to the technical scheme, on one hand, the current environment dose rate level can be determined, it is ensured that the radiation dose received by workers is within the safety limit value, and therefore the radiation risk can be reduced, and the health and safety of the workers are guaranteed; and on the other hand, specific radionuclides can be identified, so that the pollution source can be determined.

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 provides a target Her2 nuclide probe as well as a preparation method and application thereof, and relates to the technical field of nuclide probes. The target Her2 nuclide probe comprises a compound which is labeled by radionuclide and is shown in a formula I. The target Her2 nuclide probe can be used as a diagnosis and treatment reagent in human or animal Her2 protein high expression lesions, and is especially used as a tumor imaging agent and a radionuclide treatment drug. In animal experiments, the tumor / muscle ratio of the radioactive complex is high, and the radioactive complex has a good application prospect. And the formula I of the # imgabs0 # is shown in the specification.

The invention discloses a nuclear accident emergency three-layer coupling network model and a construction method, and relates to the crossing field of nuclear accident emergency management and complex system risk simulation. The nuclear accident emergency three-layer coupling network model comprises an RMN layer which is used for simulating the dynamic diffusion process of radionuclides leaked by a nuclear accident in the atmosphere; the IN layer is used for constructing a spatial distribution and dependency relationship network of infrastructures; the EN layer is used for topologically defining a command or cooperation relationship of the emergency organization; according to the three-layer network coupling mechanism, when RDR of a middle grid is larger than or equal to RDRmax-1, IN-layer nodes in the middle grid at the same position are marked to be in a damaged state; and quantifying the bidirectional dependence density of the IN layer and the EN layer through the coupling strength epsilon. The method is used for predicting the direct risk of radioactive contamination in a nuclear accident and the secondary risk caused by emergency evacuation, revealing the risk evolution law, quantifying the risk diffusion scale, determining key influence factors, and providing a theoretical basis for formulating an emergency strategy.

The invention relates to a fuel element damage monitoring method and device based on delayed neutron energy spectrum measurement. The method comprises the following steps: acquiring a delayed neutron zone for fuel element damage monitoring; according to the delayed neutron partition and the delayed neutron partition multi-column energy spectrum measurement principle, a moderator for fuel element damage monitoring is obtained; according to the moderation body and a discrimination threshold automatic identification algorithm, determining a discrimination threshold value of fuel element damage monitoring; and according to the discrimination threshold value, a few-channel spectrum unfolding algorithm and an energy spectrum peak searching algorithm, identifying neutron energy spectrum change conditions and delayed neutron precursor nuclides of fuel element damage monitoring. According to the invention, on-line real-time measurement of the delayed neutron energy spectrum can be realized, and the neutron energy spectrum change condition can be determined; according to the invention, when the delayed neutron precursor nuclide is identified, the occurrence of effective fuel element damage is judged, the online monitoring of the fast reactor fuel element damage is realized, and the rapidness and timeliness of fuel damage monitoring are improved.

The invention discloses a radioactive gas detection device and a detection method.The radioactive gas detection device is applied to detection of radioactive gas containing target nuclides and comprises an adsorption assembly, a sampling assembly, a monitoring assembly, a desorption assembly, a detection assembly, a first control valve set and a controller, the sampling assembly, the adsorption assembly and the monitoring assembly are sequentially communicated; the adsorption assembly is further communicated with the detection assembly, and the controller is configured to control the first control valve group to enable the adsorption assembly and the sampling assembly as well as the adsorption assembly and the monitoring assembly to be in a disconnected state when the monitoring assembly monitors that the radioactive gas passing through the adsorption assembly contains target nuclide; the adsorption assembly and the detection assembly are in a communication state, and the detection assembly is controlled to execute detection operation on the target nuclide released from the adsorption assembly so as to obtain the content of the target nuclide. The radioactive gas detection device can improve the detection precision of the target nuclide in the radioactive gas.

The invention provides a neutron spectrum optimization method for improving the isotope irradiation production conversion rate, and relates to the technical field of reactor engineering. Monte Carlo modeling is performed on an isotope target and related mechanisms; then Monte Carlo critical calculation is carried out, and initial neutron energy spectrums are obtained respectively; next, on the basis of the initial neutron energy spectrum, neutron energy spectrum sensitivity analysis is carried out on the target isotope; on the premise that the total neutron flux is kept unchanged, an ideal neutron energy spectrum is obtained; comparing the difference between the initial neutron energy spectrum and the ideal neutron energy spectrum, and arranging a neutron filter around an isotope target in the Monte Carlo model; then, the material type of the neutron filter is replaced, neutron energy spectrums under different material types are calculated through Monte Carlo criticality, and the material type capable of improving the target nuclide conversion rate is determined; and finally, based on the determined neutron filter material type, obtaining an optimized neutron energy spectrum. The conversion rate of isotope irradiation, namely the production efficiency of isotopes, can be improved.

The invention discloses a monocrystalline silicon neutron irradiation monitoring method and system based on a vanadium self-powered detector, and belongs to the field of nuclear engineering. The monocrystalline silicon neutron irradiation monitoring method based on the vanadium self-powered detector comprises the following steps: calculating a corresponding relation between the burnup depth and nuclide components of a fuel assembly and a corresponding relation between axial burnup distribution of the fuel assembly and fuel circulation and the burnup depth; calculating to obtain a corresponding relationship between the thermal neutron fluence rate of the irradiation pore channel and the burnup cycle and the burnup depth; and taking a position where the thermal neutron fluence rate of the irradiation pore channel does not exceed a given threshold value as a detector mounting area, and calibrating a corresponding relation between a vanadium self-powered detector signal mounted in the detector mounting area and the thermal neutron fluence rate of the irradiation pore channel by using an activated foil, thereby monitoring the thermal neutron fluence rate of the monocrystalline silicon by using the vanadium self-powered detector.

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 invention discloses a nuclear power plant reactor core fuel assembly uranium contamination fission product calculation method and system, and the method comprises the following steps: monitoring the characteristic nuclide of a loop coolant of a reactor core fuel assembly in real time, and judging whether the surface of the reactor core fuel assembly has uranium contamination; if the uranium contamination exists, calculating the uranium contamination amount of the uranium contamination distributed in the primary loop coolant on the surface of the reactor core fuel assembly; and calculating uranium contamination fission product distribution of the reactor core fuel assembly according to the uranium contamination amount. According to the method, the uranium contamination fission product distribution in the primary loop coolant is collected, so that the risk of erroneous judgment of the damage of the reactor core fuel assembly caused by uranium contamination can be remarkably reduced.

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 discloses a nuclear power plant reactor core fuel assembly damage analysis and calculation method and system. The method comprises the following steps: calculating a typical nuclide equivalent attenuation coefficient according to fission product source item characteristics; calculating a typical nuclide release rate according to the typical nuclide equivalent attenuation coefficient; according to the equivalent attenuation coefficient of the typical nuclide and the release rate of the typical nuclide, calculating the reachable equilibrium specific activity of the typical nuclide; by analyzing typical nuclides, equilibrium specific activity can be achieved, and reactor core fuel assembly damage analysis is carried out. According to the method, the equilibrium specific activity can be reached through typical nuclides to carry out reactor core fuel assembly damage analysis, and the operation reliability of the reactor core fuel assembly is analyzed.

The invention relates to a method for evaluating the radiation dose of special public nearby a nuclear facility, and the method comprises the steps: estimating the concentration distribution of radionuclides in air, surface soil and a biological medium nearby the nuclear facility through collecting the radiation dose evaluation parameters of a target special public and combining an environment quality evaluation model; based on the data, the annual effective dose of the target special public at the nuclear facility boundary and the living quarter is calculated, and a plurality of ways such as inhalation internal irradiation, air immersion external irradiation, surface deposition external irradiation and ingestion internal irradiation are considered. In addition, a dynamic calculation method is also introduced, especially for the influence of year-by-year change of the cumulant of radionuclides deposited on the earth surface, factors such as decay, resuspension and infiltration into underground water of nuclides are fully considered, and the accuracy and foresight of evaluation are improved. Accurate and comprehensive technical support is provided for radiation protection of the special public around the nuclear facility, and the requirements of the nuclear facility public for dose monitoring and risk management are met.

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 Ga-68 activity direct measurement method which comprises the following steps: S1, preparing Ga-68 samples including a measurement sample and a blank sample; s2, establishing a mathematical model of the detection efficiency of the Ga-68 sample, including the detection efficiency epsilon D that double tubes of a single particle conform to D and the detection efficiency epsilon T that three tubes of the single particle conform to T; s3, establishing measurement equations based on the relationship between the measured total count and the mathematical model of the Ga-68 sample detection efficiency, including the measurement equations corresponding to the total detection efficiency epsilon total, D of the sample under the condition that double tubes conform to D and the measurement equations corresponding to the total detection efficiency epsilon total, T of the sample under the condition that three tubes conform to T; and S4, calculating the Ga-68 activity based on the measured sample count and radionuclide detection efficiency. The method provided by the invention meets the requirements of simple and convenient sample preparation, recyclable nuclide and low uncertainty.

The present invention belongs to the technical field of radiopharmaceutical chemistry and nuclear medicine diagnosis and treatment and relates to a radiolabeled FAPI complex, a preparation method therefor, and a use thereof. The general structural formula of FAPI capable of realizing radionuclide labeling is as shown below: wherein R is a nitroimidazole group or -COOH; X is a chelating group or a chelating structure chelated with a radionuclide; L1 and L2 are linking groups; and A is an adjusting atom of an FAP-targeting group, and all the A atoms are H atoms or F atoms. The synthesis method for a radionuclide-labeled precursor of the present invention is simple and suitable for various nuclide labels, the labeling method is convenient, and the label has high radiochemical purity and good stability. The radiolabeled FAPI complex shows high affinity and specificity for FAP in a cell experiment and a high tumor uptake and target to non-target ratio in a tumor-bearing mouse, and is a potential FAP-targeting radioactive diagnosis and treatment drug.

A portable small protective workstation for alpha nuclide operation comprises a protective cabin, a transparent window and glove holes are formed in the front side face of the protective cabin, radiation-resistant operating gloves are embedded in the glove holes in a sealed mode, a tray inlet is formed in the side face of the protective cabin, and a drawer type bracket is connected to the tray inlet in a sliding mode. The drawer type bracket comprises a tray layer, a cushion layer and a cover plate, the tray layer and the cushion layer are both vertically and fixedly connected to the side face of the cover plate, the tray layer is located above the cushion layer, a high-adsorbability radioactive water absorption pad is fixedly installed on the cushion layer, a plurality of through holes are formed in the bottom face of the tray layer, and the tray layer and the cushion layer are movably installed in the protection cabin body through a tray inlet. The cover plate abuts against the outer side face of the protection cabin in a sealed mode. An air filter box is arranged above the protective cabin body, and a filter layer is arranged in the air filter box. According to the utility model, the defects in the prior art are overcome, and the organic unification of radiation protection, pollution control and experiment convenience for operators is realized.

The invention discloses a compensation method and system for continuously, rapidly and accurately measuring the radon concentration in air, and the method comprises the steps: taking the number of nuclides in a measurement cavity at the initial moment of a current sampling period as an initial value, and obtaining a time-varying function of the number of nuclides in the measurement cavity in combination with a gas exchange and nuclide decay model; determining the theoretical total count of alpha particles in the current measurement period, and establishing a relational expression between the count of the alpha particles and the number of nuclides; based on the relational expression and the actual measurement count, the number of environmental radon atoms is obtained, and the radon concentration is calculated in combination with a radon decay constant; and finally, combining the number of radon atoms at the current sampling point and a model containing gas exchange and nuclide decay to obtain the nuclide number at the end of sampling, taking the nuclide number as the initial state of the next sampling period, switching the sampling points, and repeating the steps to realize continuous, rapid and accurate sampling. According to the method, through loop iteration, the balance waiting time is effectively saved, and continuous, rapid and accurate measurement of the radon concentration in the environment by a single radon measuring instrument is realized.

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.