186 results about "Activity concentration" patented technology

A method of controlling an 82Sr / 82Rb elution system having a generator valve for proportioning a flow of saline solution between an 82Sr / 82Rb generator and a bypass line coupled to an outlet of the generator such that saline solution traversing the bypass line will merge with eluted saline solution emerging from the generator to provide an active saline solution. During each elution run, a plurality of successive concentration parameter values are obtained at predetermined intervals. Each concentration parameter value is indicative of a respective instantaneous activity concentration of the active saline solution. Respective error values between each concentration parameter value and a target activity concentration value of the elution run are computed. Error data based on a plurality of the computed error values is accumulated. Between successive elution runs, at least one performance parameter of the elution system is adjusted based on the accumulated error data.

A particulate coformulation, each particle comprising a core of an active substance surrounded by an excipient coating, the particles having a volume mean diameter of 10 μm or less, which on oral administration releases the active substance at a rate such that the time (Tmax) taken to attain the maximum active concentration in the bloodstream is one hour or less. The coformulation may be made using a Nektar™ SCF particle formation process.

The invention discloses a quantitative determination method for activity of a nerve growth factor. The method comprises the following steps of: (1) washing TF-1 cells in a logarithmic phase by a basal culture medium that contains no serum and recombined human granulocyte-macrophage colony stimulating factors, and then resuspending the TF-1 cells to obtain TF-1cell suspension liquid; (2) respectively adding the TF-1cell suspension liquid into a gradient-diluted nerve growth factor standard sample and a sample to be tested, and incubating at 37 DEG C in presence of 5% of CO2; then respectively adding an indicating agent to detect the absorbance / fluorescence value and drawing a standard curve line; and (3) calculating the activity concentration of the nerve growth factor of the sample to be tested according to the standard curve line and the absorbance / fluorescence value of the sample. The quantitative determination method for activity of the nerve growth factor disclosed by the invention has good accuracy and precision.

The invention relates to an alpha and gamma dual-channel energy spectrum continuous monitoring method and an alpha and gamma dual-channel energy spectrum continuous monitoring system. The method and the system are characterized in that a power supply device provides an operating voltage for the monitoring system; a boosting device, a sampling device, a measuring device and a sample transmission device transmit respective status signals to an upper computer through a driving and status feedback module, the upper computer controls the boosting device to cooperate with the sampling device through the driving and status feedback module so as to sample environmental airborne radioactive substances, and samples are transmitted to the measuring device through the sample transmission device; the upper computer controls the boosting device to match with the measuring device through the driving and status feedback module so as to measure alpha-ray particles and gamma decay photons released by the samples to obtain analog pulse signals, the analog pulse signals are transmitted to a signal preprocessing unit for processing to obtain alpha and gamma measurement spectral lines, and the spectral lines are transmitted to the upper machine; the upper computer calculates to obtain activity concentration of the sampled environment, and displays, stores and transmits the activity concentration to a central processor.

The invention relates to a sensor, in particular to a polymer liquid film potential sensor for detecting enzymatic activity and a detection method thereof. A potential detector is respectively connected with an internal reference electrode and an external reference electrode through wires, the internal reference electrode is inserted in a working electrode filled with internal liquid, the working electrode and the external reference electrode are inserted in a detection pool with detection liquid, the working electrode is an electrode carrier on which a polymer sensitive film is fixed, and a power device with a solution disturbance function is arranged in the detection pool. According the detection method, the potential detector is used for detecting the change of the potential of the polymer sensitive film at the bottom of the working electrode before and after enzymatic reaction, and the enzymatic activity concentration can be detected on the basis of a standard working curve according to a potential change signal. The potential sensor has the advantages of high generality, good selectivity, high sensitivity and low cost and is suitable for detection under a complicated matrix condition.

A method of controlling an 82Sr / 82Rb elution system having a generator valve for proportioning a flow of saline solution between an 82Sr / 82Rb generator and a bypass line coupled to an outlet of the generator such that saline solution traversing the bypass line will merge with eluted saline solution emerging from the generator to provide an active saline solution. During each elution run, a plurality of successive concentration parameter values are obtained at predetermined intervals. Each concentration parameter value is indicative of a respective instantaneous activity concentration of the active saline solution. Respective error values between each concentration parameter value and a target activity concentration value of the elution run are computed. Error data based on a plurality of the computed error values is accumulated. Between successive elution runs, at least one performance parameter of the elution system is adjusted based on the accumulated error data.

The invention discloses a PIG sampling and monitoring system and a method, comprising a sampling loop unit and a radioactivity measurement analysis control unit. The sampling loop unit comprises an aerosol accumulation sampling subunit and a radioactive gas accumulation sampling subunit; the aerosol accumulation sampling subunit comprises a filter; the radioactive gas accumulation sampling subunit comprises a gas accumulation sampling device and a molecular filtering film; the radioactive measurement analysis control unit comprises an HPGe detector, an energy spectrum analysis meter and a computer. The HPGe detector performs measurement on the radioactivity of the above subset units at the same time; the energy spectrum analysis meter processes the measurement information and gives out the radioactivity energy spectrum information; the radioactivity energy spectrum information and the flow control information of the sampling loop unit are transmitted to the computer for processing to obtain activity concentration of all nuclides in the airborne fluid. The invention realizes the accumulated sampling measurement on the PIG in the airborne fluid, improves the accuracy of radioactivity nuclide measurement in PIG, and has better practicability.

The invention discloses a novel system and method of measuring concentration of radon in water. The novel system of measuring concentration of radon in water includes successively connected first Gamma detector, first linear amplifier, first single-channel pulse-height analyzer, first delay shaping circuit and first scaler, and successively connected second Gamma detector, second linear amplifier,second single-channel pulse-height analyzer, second delay shaping circuit and second scaler, wherein the output terminal of the first delay shaping circuit and the output terminal of the second delayshaping circuit are connected to the input terminal of a coincidence circuit; the coincidence output terminal of the coincidence circuit is connected with a third scaler; the novel system of measuring concentration of radon in water also includes a calculation module which is used for calculating the activity concentration C<222><Rn>: C<222><Rn>=n<Gamma Gamma 1> - n) / V<Elipson> <Gamma Gamma>of 222Rn in a sample to be measured, wherein n<Gamma Gamma 1> is the counting rate of the third scaler during the process of measuring the sample to be measured; n is the background counting rateof the third scaler; V is the volume of the sample to be measured; and Epsilon <Gamma Gamma> is the detection efficiency of a coincidence channel. The novel system and method of measuring concentration of radon in water can quickly reduce the measurement background and can achieve the effect of quickly and accurately measuring the concentration of radon in water.

The invention discloses a storage method and device of a supervision video, and belongs to the technical field of supervision. The method comprises the steps: recording the frequency of a movable frame in the picture recording process, wherein the movable frame refers to a key frame with the size exceeding a peace range; counting the activity concentration ratio according to the time of the movable frame and the preset time interval; carrying out associative storage for a recording time of a picture recording file, the frequency of the movable frame and the activity concentration ratio to be used as an important judgment evidence of the picture recording file when the picture recording file is stored. By adopting the storage method and device, the variation of the key frame of the picture recording file, the recording time and the activity concentration ratio are combined and associatively stored so as to provide the evidence for judging the importance of the picture recording file. In addition, in the circulating storage process of the supervision video, when the storage space is insufficient, the variation of the key frame and the recording time are combined to judge the importance of the picture recording file, so that the picture recording file with low importance can be deleted first, the space can be released for recording new video, and the important historical picture recording file is prevented from being deleted.

The invention discloses a water body gamma radiation stereoscopic monitoring system and method based on an autonomous underwater vehicle. Modular design is adopted, and the water body gamma radiationstereoscopic monitoring system comprises a gamma radiation detection module, a control module, an energy module and a power module; the gamma radiation detection module extracts gamma radiation in real time, quickly judges whether artificial radioactive nuclides exist or not through a deep learning network system, and collects detection data; the control module adopts an intelligent path planningsystem with Gaussian process regression to control the autonomous underwater vehicle to conduct intelligent cruising according to the gamma radiation measurement result. By means of the water body gamma radiation stereoscopic monitoring system, it can be achieved that stereoscopic distribution of the activity concentration of gamma radiation nuclides in the water body can be efficiently and precisely measured.

The invention belongs to the field of radiation protection, and provides a system platform for calibrating radioactive aerosol monitoring equipment and a working method thereof. The platform comprises an aerosol generation device, a standard aerosol activity concentration measurement device, a to-be-calibrated aerosol monitoring equipment device, an aerosol recycling device, an electrical control and monitor console, and the like. According to the invention, radioactive aerosol generated by the aerosol generation device simultaneously flows through the standard aerosol activity concentration measurement device and the to-be-calibrated aerosol monitoring equipment device, the obtained radioactive activity concentration is equal, the standard aerosol activity concentration measurement device goes through standard measurement and can accurately measure the activity concentration values of gaseous radioactive aerosol of different activity levels and different types, and thus, a to-be-calibrated detector can be calibrated. The system platform has the advantages of dynamic calibration, high precision, adjustable measurement range, synchronous measurement by the standard device and the to-be-calibrated device, applicability to online monitoring and offline monitoring, and the like.

The invention discloses an underwater radiation monitoring method and system. The underwater radiation monitoring system comprises a detecting module, a pulse processing module, an energy spectrum analyzing module and a power supply module, wherein the detecting module is used for detecting rays emitted by radiating particles in the water and converting the rays into electric pulse signals, and the detecting module comprises a plurality of detectors; the pulse processing module is used for amplifying and screening the electric pulse signals to generate pulse energy spectrum data; the energy spectrum analyzing module is used for analyzing pulse energy spectrum data by an anticoincidence method and a virtual efficiency graduation program to obtain nuclide activity concentration of radioactive substances; and the power supply module is used for supplying power to the detecting module, the pulse processing module and the energy spectrum analyzing module. According to the system of the embodiment of the invention, the plurality of the detectors are used for converting the rays emitted by the radiating particles in the water into electric pulse signals for monitoring, and the energy spectrum analyzing module is used for analyzing the measured signals, so that the nuclide activity concentration of radioactive substances is identified, the measuring efficiency and the nuclide distinguishing effect of the system are improved, and the influences of the environment radioactive factors to the measured result are lowered.

The invention discloses an evaluation method for space activity concentration of an airborne radioactive substance source of a nuclear power plant. The evaluation method comprises the following steps: aiming at each decay chain of radionuclides, generating decay-migration grids and storing derived decay-migration chains; aiming at each space and each radionuclide in the decay-migration grids, obtaining path numbers from the decay-migration at a starting point to each space-radionuclide grid point and path numbers from the decay-migration of each space-radionuclide grid point to an ending point; aiming at each decay-migration chain, obtaining the activity concentrations of relevant radionuclides in each space according to the corresponding decay constant and removal ratio; accumulating the activity concentrations of the relevant radionuclides of all decay-migration chains in all spaces and comparing the accumulated value with a preset space activity concentration threshold of the relevant radionuclides. According to the technical scheme, accurate evaluation of the airborne radioactive substance source is realized by using a linear subchain technology.

An embodiment of the invention provides a normalized correction factor obtaining method and device and a medical imaging method, relates to the technical field of image processing and can reduce calculation errors of each element of normalized correction and mutual interference and residues. The mormalized correction factor obtaining method comprises the following steps: in the homogeneous phantom decay process, obtaining activity concentration of a homogeneous phantom under specific activity, phantom position, scanning data and a normalized correction factor; according to the activity concentration and the phantom position, obtaining a first reconstructed image of the homogeneous phantom, and carrying out normalized correction on the scanning data by utilizing normalized correction factor to obtain a second reconstructed image of the homogeneous phantom; mapping the first reconstructed image and the second reconstructed image to chordal graph domains respectively; carrying out projection comparison to obtain a correction term of the normalized correction factor; and according to the correction term, correcting the normalized correction factor under the specific activity. The technical scheme is suitable for the correction process of the normalized correction factor.

A method of determining active concentration of an analyte in a sample comprises the steps of:(a) contacting a laminar flow of the sample with a plurality of solid phase surfaces or surface area supporting a ligand capable of specifically binding the analyte, each surface or surface area having a different ligand density,(b) determining the initial binding rate (dR / dt) of analyte to the ligand at each ligand-supporting surface or surface area,(c) from the determined initial binding rates determining the initial binding rate corresponding to transport-limited interaction at the surfaces or surface areas, and(d) from the initial binding rate determined in step (c) determining the active analyte concentration.

This invention relates to a dehydrogenation catalyst having a macropore size and a high active density of platinum, suitable for use in dehydrogenation of a hydrocarbon gas. This dehydrogenation catalyst having a macropore size and a high active density of platinum is highly active, has high active density per unit catalytic surface area, facilitates material transfer of reactants and products, delays deactivation due to coke formation, keeps the initial activity constant after being regenerated thanks to the disposal of coke, has high strength and so is resistant to external impact, and undergoes neither structural changes due to heat nor changes in the properties of active materials.

The invention provides an electrochemical method used for measuring activity of alkaline phosphatase and an electrochemical sensor used in the method. The method comprises the following steps: preparing an electrode modified by cysteine and copper ions; drawing a standard curve between the enzyme activity concentration of alkaline phosphatase and relative current intensity under a pyrophosphate ion substrate with specific concentration; changing the alkaline phosphatase solution with known enzyme activity concentration into a to-be-measured sample containing alkaline phosphatase, performing cyclic voltammetry scanning to obtain the relative current intensity, and calculating to obtain the activity concentration of the alkaline phosphatase in the to-be-measured sample according to the standard curve. According to the method disclosed by the invention, a reversible competitive coordination principle of the cysteine, pyrophosphate ions and copper ions is utilized, the electrochemical sensor used for measuring the activity of alkaline phosphatase is prepared, and the activity of alkaline phosphatase can be rapidly, simply and accurately measured by utilizing the electrochemical sensor.

The invention relates to a method for detecting activity of catalase, belonging to the field of enzymatic activity detection methods. The method for detecting activity of catalase comprises the following steps: diluting a catalase standard substance into a standard solution with a series of catalase activity concentrations, adding 10mL of chlorine peroxide phosphate buffer solution in a 100mL iodine measuring flask, putting the iodine measuring flask in water bath at 25 DEG C and carrying out heat preservation, then adding 2mL of a standard enzyme solution, accurately carrying out heat preservation for 3 minutes, instantly adding 2mL of 0.5mol / L sulfuric acid to end reaction, adding 2mL of 0.5mol / L sulfuric acid into a contrast tube of a contrast reaction solution to end reaction, and then adding the enzyme solution; then extracting 0.1mL of the reaction solution, adding 2.9mL of a peroxidase-dianisidine solution in a test tube and shaking to be uniform, firstly carrying out zero adjustment by a blank test tube in 436microns by virtue of a spectrophotometer at 25 DEG C, then detecting absorbancy of each reaction solution test tube to obtain a curve about the relation between the standard enzymatic activity and the absorbancy. The test enzyme is processed by the same method, so that the enzymatic activity of the test enzyme can be obtained according to the absorbancy and the standard curve. The detection method has the characteristics of being accurate, high in practicability, simple in instrument requirement and suitable for operation in the conventional condition; the detection method belongs to one reliable method of color rendering methods for detecting the activity of the catalase.

The invention relates to an analysis method of <210>Po in aerosol. The analysis method includes steps: (1) acquiring an aerosol sample; (2) adding a tracer <209>Po (IV); (3) adding 6-12 mol / L of hydrochloric acid, leaching <210>Po in the detected sample, performing filtering, evaporating filtrate until the filtrate is almost dry, and cooling the filtrate to a room temperature; (4) adding 0.1-1 mol / L of hydrochloric acid and reducing agents into a filtrate dry product and performing mixing; (5) putting a metal plating sheet whose potential is lower than that of Po (IV) ions into an auto-deposition sample solution, performing heating and sealed condensation, and enabling the Po(IV) ions to be self-deposited on the metal plating sheet; (6) taking out the metal plating sheet, and cleaning and drying the metal plating sheet; (7) measuring the counting of Po; and (8) calculating the activity concentration of <210>Po in the detected sample according to the counting of <209>Po and <210>Po and the activity of <209>Po. By employing the analysis method, high whole recovery rate of <210>Po can be obtained, the stability is good, and the accuracy is high.

The invention discloses an antibacterial peptide composite material and a preparation method and application thereof and belongs to the technical field of biomedicine. An antibacterial peptide-graphene composition material is prepared by using natural antibacterial peptide and a small-size graphene material as raw materials and adopting a chemical modification or physical adsorption method. The material has good antibacterial ability and low hemolytic toxicity within an activity concentration range. Especially, antibacterial efficiency of a melittin / graphene oxide composite material prepared by the method is higher than more than 20 times than that of original melittin or graphene oxide. The characteristic that antibacterial peptide and graphene material have similar mechanism of damagingcell membranes is utilized, the antibacterial peptide and the graphene material are synergistic to realize quick and efficient inserting and pore-forming of the cell membranes so as to cause leakage of bacterial content, and effective bacteria killing at extremely low drug concentration is realized.

The present invention provides a method for quickly investigating and evaluating the radioactive radiation environment of a coalfield with multiple parameters on site, which uses a multi-channel gamma energy spectrometer on the ground or in a well to measure natural uranium, uranium, The nuclide content of thorium and potassium and the total radioactivity of gamma can be used to calculate the activity concentration of uranium, thorium and potassium in the coal field by using the conversion coefficient of the radionuclide content and the activity concentration unit; according to the activity concentration of uranium, thorium and potassium in the coal field On-site calculation of gamma radiation dose rate; on-site estimation of the effective dose equivalent of coal field environment gamma radiation to residents based on gamma radiation dose rate; finally, this technology can replace laboratory analysis and on-site gamma radiation dose rate measurement, and provide uranium, thorium, Nuclide content of potassium, activity concentration of uranium, thorium, and potassium, environmental gamma radiation dose rate, effective dose equivalent of gamma radiation to residents, in order to achieve rapid, economical and multi-parameter completion of coal field radioactive radiation environmental investigation and evaluation.

The invention relates to a 5'-nucleotidase diagnosis reagent box of Enzymatic Recycling Method, and the invention also relates to method principle for detecting the solution of 5'-nucleotidase, constitute and component of reagent, which belongs to the technical field of medical checking measurements. The reagent box in the invention can be dry powder state, and used after dissolution; it also can be formulated to be liquid agent for direct usage. The component of reagent box mainly contains: buffering liquid, alpha- ketoglutaric acid, reduction type coenzyme, Adenosine Deiminase EC 3.5.4.4, glutamate dehydrogenase EC 1.4.1.2, EC 1.4.1.3, EC 1.4.1.4, Glutamate oxidase EC 1.4.3.7, EC 1.4.3.11, peroxidase EC 1.11.1.7, reduction type chromogen assembly, stabilizer and anti-interference agent; and the component can be mixed to form single-reagent reagent box, two-reagent reagent box, and three-reagent reagent box; by series of enzymatic reaction, the colorless reduction type chromogen assembly is oxygenated to form color dye, and the content of dye can be measured by visible light analyzer at wavelength of 400-700nm to reflect the concentration of 5'-nucleotidase directly. Comparing with present technique, the invention can be spread easily, and because the produced dye has higher molar extinction coefficient, the sensitivity is high, and the precision is well.

The invention provides a main steam pipeline radiation monitor method and a device thereof. The method includes: setting a 16N radiation monitor and an inert gas radiation detector in a main steam pipeline, wherein that 16N radiation monitor judges the leakage condition of a steam generator by monitoring 16N nuclide and the inert gas radiation detector monitors the total activity concentrations of85Kr and 133Xe in the main steam pipeline; a 16N in situ radiation processing module is connected to the 16N radiation monitor, and an inert gas in situ radiation processing module is connected to the inert gas radiation detector. A computer control section is connected to the 16N radiation monitor and the inert gas radiation detector, the 16N radiation monitor and the inert gas radiation detector receives a control signal of the computer control section, transmits the measured radiation data, and gives an acoustic and optical alarm and indication signal.

The invention discloses a method of processing waste resin of a nuclear power plant. The method comprises following steps: extracting a predetermined amount of APG waste resin from a randomly chosen object; measuring at least one gamma nuclide of the APG waste resin by a gamma spectrometer system and a dosage rate instrument, obtaining multiple parameters through detection; according to the parameters, carrying out calculation to obtain the activity concentration value of gamma nuclide, comparing the activity concentration value of gamma nuclide with a control release limited value; if the activity concentration value of gamma nuclide is not greater than the control release limited value, taking the APG waste resin as normal wastes; and if the activity concentration value of gamma nuclideis greater than the control release limited value, taking the e APG waste resin as radioactive wastes. The processing method has the advantages that slightly polluted APG waste resin is divided into APG waste resin that meets the control release requirements and APG waste resin that does not meet the control release requirements; the divided APG waste resin is processed individually, the processing efficiency is improved, the processing amount of radioactive wastes is reduced, the safety for the method of processing radioactive resin is improved, and the waste processing cost is reduced at thesame time.

The invention relates to an on-spot estimation method of the radioactive waste quantity. In order to overcome defects existing in radioactive waste quantity estimation of the existing source item investigation work, the invention puts forward the on-spot estimation method of the radioactive waste quantity. The method comprises the following steps: (1), selecting a dosage rate field measurement instrument meeting the requirement; (2), coating the outside of the dosage rate field measurement instrument with lead and steel to form a shielding body with an opening formed at the lower end to form an orientated measuring device, and carrying out scaling on the orientated measuring device; (3), carrying out on-spot measurement on the orientated measuring device so as to obtain a response-activity concentration curve; (4), on the basis of keeping the original landform, carrying out oriented measurement on the pollution level of the ground radioactive waste; and (5), according to the overall situation of the field measurement, directly estimating the total amount of various radioactive wastes. With the estimation method, the sampling analyzing period can be shortened obviously; the work progress of the source item investigation is accelerated; and the cost is low.

The invention discloses a method for monitoring radioactive substances in a nuclear power plant control room. The method comprises the following steps: acquiring activity concentration of radioactive substances in air of the nuclear power plant control room; monitoring whether the external irradiation dose and internal irradiation dose of the control room reach values which harm a human body; if so, transmitting an alarm signal. A comprehensive and reliable technology for monitoring and processing the radioactive substances in the nuclear power plant control room is realized. In addition, the invention also discloses a system for monitoring radioactive substances in the nuclear power plant control room.

The invention relates to a method for measuring the activity concentration of kalium-subtracted total beta radionuclides in seawater, and the method is characterized in that the method comprises the following steps: (a) adding a cobalt carrier into used seawater, forming cobalt ion solution, adjusting the pH value of the cobalt ion solution to be greater than seven, and then adding thioacetamide into the solution to form cobalt sulfide sediments through reaction; (b) extracting and putting the cobalt sulfide sediments under the temperature from 600 DEG C to 800 DEG C for ashing; (c) adding porphyrized ashing products to a measuring disc, adding an ethyl alcohol sample, and putting the mixture on a flow-gas type proportional counter for measurement and calculation. The method achieves the measurement of beta radionuclides with the enrichment ratio being greater than 95% which is discharged into the seawater in an operation process of nuclear facilities, such as 58Co, 60Co, 59Fe, 65Zn, 110mAg and so on, thereby guaranteeing that the sediments prepared through the method are more uniform and moderate in weight. The detection lower limit is 3mBq / L, so the method is suitable for the monitoring of the activity concentration of kalium-subtracted total beta radionuclides in seawater, and is also suitable for heavy-salt water similar to a seawater sample, and heavy-salt water which contains radionuclides and is obtained through processing.

The 3D image generation with position-sensing gamma probe utilizes a gamma probe connected to a control unit. The control unit is also connected to a display unit. A probe contact surface feeds position information to the display unit. The gamma probe is moved across a region of interest over the probe contact surface, generating position-dependent gamma rates with the help of the control unit. The probe contact surface is utilized to determine the position of the probe head and provides position information, which, together with the gamma rate, enables generation of a rate map in the display unit. This allows producing 2D and 3D images of gamma activity concentrations and assures proper recording of scan data. The scanning area of interest is pre-defined by frames having shapes and contours optimized for intended applications. 2D and 3D images can be obtained in a single scanning cycle.

The embodiment of the invention provides a radioactive inert gas measurement device and method, equipment and a storage medium. According to the device, signal detection equipment detects a beta-gammacoincidence pulse electric signal obtained through the action of a sample and a detection crystal, and a beta detection crystal and a gamma detection crystal in a detector are arranged in a combinedmanner; the beta-gamma coincidence pulse electric signal is converted into a digital form from an analog form by signal acquisition and processing equipment; a computing device analyzes the amplitudeof the beta pulse signal in the beta-gamma coincidence pulse electric signal to obtain a first amplitude and the amplitude of the gamma pulse signal to obtain a second amplitude; and the activity concentration of the inert gas nuclide in the sample is calculated according to the pulse count of the digital beta-gamma coincidence pulse electric signal in the amplitude range formed by the first amplitude and the second amplitude. According to the scheme, the accuracy and reliability of measurement can be improved, radioactive inert gas nuclides can be distinguished, the concentration value of activity can be accurately and continuously measured, and the size, weight and cost of the detection device can be reduced.