186 results about "Activity concentration" patented technology

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 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 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 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.