51 results about "Gamma dose" patented technology

The invention provides a BNCT important clinical parameter prediction method based on a BP neural network. The method comprises the steps of obtaining neutron energy spectrum and dose distribution data; constructing a multi-layer BP neural network model and training the multi-layer BP neural network model; selecting a treatment position of an outlet of a beam shaper of the BNCT as a point to be measured, and measuring a neutron energy spectrum and neutron distribution at the measurement point; using the trained multilayer BP neural network model to predict distribution of boron dose, hydrogen dose, nitrogen dose and gamma dose in tumors and normal tissues in a human body corresponding to neutron energy spectrum and neutron distribution, and calculating related clinical parameters. According to the method, the neutron source for the BNCT can be rapidly and accurately evaluated, uncertainty and risks in treatment can be reduced through accurate parameter prediction, and the safety of the BNCT is improved; reliable parameter prediction is provided for clinicians, the accuracy and efficiency of clinical decision making are improved, the treatment process is optimized, and therefore the overall medical cost is reduced.

The invention relates to the field of post-accident gamma dose rate measurement, and provides a post-accident gamma dose rate dynamic measurement method and system based on multi-detector fusion, and the method comprises the steps: obtaining original signal data and environment parameter data; processing the original signal data, the environmental parameter data, the accumulated radiation dose and the displacement damage energy by adopting a deep learning network to obtain corrected signal data; processing the correction signal data and the environmental parameter data through a time sequence prediction network to obtain a dynamic weight distribution result of each detector; processing the correction signal data and the dynamic weight distribution result based on a self-calibration confidence evaluation network to obtain a confidence evaluation result; and processing the correction signal data, the dynamic weight distribution result and the confidence evaluation result through a weighted fusion algorithm to obtain a dynamic measurement result of the gamma dose rate after the accident. According to the invention, high-precision dynamic measurement, real-time damage compensation and nuclear safety level reliability evaluation of the gamma dose rate after an accident are realized.

The present invention relates to the field of nuclear radiation monitoring technology, and specifically to a nuclear radiation monitoring method and system for improving the accuracy of gamma dose rate prediction, comprising the following steps: collecting data based on an automatic monitoring station, recording gamma radiation dose rate data and time information in real time, collecting environmental information and meteorological information around the monitoring station, and generating radiation data collection records. In the present invention, by real-time recording and analysis of environmental and meteorological information, real-time adjustment of data processing parameters is performed to reduce the interference of environmental and meteorological parameters on prediction results, improve the quality of monitoring data and the reliability of prediction models, adjust the layout of monitoring stations, improve the efficiency and response capability of monitoring networks, combine data from multiple monitoring stations, adjust the predicted model parameters, optimize the stability and accuracy of prediction models in various environments, improve the ability of environmental safety and public health protection, and enhance the safety management capabilities of nuclear facilities and environmental radiation monitoring.

This invention discloses a method for estimating radioactive release during the preparation of radioactive metal waste, comprising the following steps: (1) conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; (2) setting up monitoring points in the radioactive metal waste areas with different pollution levels, and calculating the radioactive residue in the metal waste based on the monitoring data; (3) calculating the total release of each nuclide in the metal waste based on the above-mentioned radioactive residue in the metal waste and the obtained concentration data of radionuclides in the metal waste. By conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; setting up monitoring points in the delineated areas to obtain the radioactive residue in the metal waste; and calculating the total release of each nuclide using formulas, the process is simple, easy to operate, and can obtain effective data on the total release of nuclides, providing data support for the preparation of radioactive contaminated metal waste and supporting the assessment of the dose caused by contaminated metal waste to the public.

The invention relates to the field of gamma dose rate monitoring, and provides a high-altitude radioactive point source dose rate distribution analysis method and system, and the method comprises the steps: collecting original counting data and energy spectrum data, and obtaining environment parameter data and flight carrier position information; performing statistical calculation on the original counting data to obtain counting statistical parameters; performing nonlinear correction on the original counting data, the energy spectrum data, the environmental parameter data and the counting statistical parameters to obtain corrected detector data and measurement uncertainty; performing fusion calculation on the corrected detector data to obtain a fusion weight, and performing verification processing to obtain fusion dose rate data; performing prediction processing on the fused dose rate data and the environmental parameter data to obtain a range switching signal; and performing reconstruction processing on the fused dose rate data, the range switching signal, the measurement uncertainty and the flight carrier position information to obtain ground dose rate distribution data. According to the invention, the accuracy and reliability of high-altitude radioactive point source dose rate distribution analysis are improved.

The invention relates to the related technical field of measurement and calibration, in particular to a signal processing and calibration method and device for a long-rod type gamma dose rate instrument and a medium. The method comprises the following steps of: acquiring a real-time electric signal generated by the long-rod type gamma dose rate instrument by adopting a multi-sampling method, and converting the electric signal into a pulse signal; carrying out noise removal processing and abnormal value elimination processing on the pulse signals, and carrying out summary analysis to obtain a target pulse number; environment information and information of the long-rod type gamma dose rate instrument are collected, and a preset coefficient is corrected based on the environment information and attitude information of the long-rod type gamma dose rate instrument; calculating a ratio between the preset coefficient and the target pulse number; the ratio is gamma dosage rate. Through the arrangement, the obtained measurement result is more accurate.

The invention discloses a method for measuring a body source dose rate under strong line source interference. The method comprises the following steps: step 1, measuring a gamma dose rate Dair at the same height in a nearby non-pipeline interference area through a gamma dose rate monitor; 2, calculating to obtain a gamma dose rate contribution ratio as a constant k; 3, measuring gamma dose rate measured values M1 and M2 at h1 and h2 positions on the central axis of the pipeline through a gamma dose rate monitor; 4, the gamma dosage rate caused by the air in the monitoring area is evaluated according to the value k, the M1 and the M2, and rapid early warning is carried out. The gamma dosage rate caused by the ambient air can be obtained by changing the position of one gamma dosage rate monitor; according to the method, the problem that ambient air radioactivity early warning cannot be realized through a gamma dose rate instrument in a part of strong radioactive pipeline passing areas in a plant is solved, the monitoring cost of radioactive gas leakage in the plant can be expected to be reduced, and the monitoring timeliness is improved.

The utility model relates to the technical field of nuclear air purification, and particularly discloses intelligent air purification iodine removal equipment which comprises an equipment body, an air inlet pipeline is connected to the top of one side of the equipment body, an exhaust pipeline is connected to the bottom of the other side of the equipment body, one end of the air inlet pipeline is connected with an air inlet buffer tank, and the other end of the air inlet buffer tank is connected with an air outlet. According to the iodine removal equipment, the air inlet buffer box is arranged, so that airflow is increased, the contact area between a filter and air is increased, the filter can conduct uniform filtration, various sensors are adopted for real-time monitoring, and the iodine removal equipment is high in practicability and high in practicability. Data of temperature and humidity, gamma dosage rate, pipeline pressure difference and wind speed during operation each time can be recorded in real time, packaged and uploaded to an upper computer, detachable box doors are further fixed to the air filter box, the iodine adsorption box and the fan box through rubber head hand screws, daily maintenance and overhaul are facilitated, and the equipment is high in automation degree and high in efficiency. And the blockage or fault part can be judged according to the data of the pressure difference transmitter.

A non-destructive inspection system includes: a neutron emission unit capable of emitting neutrons having a first neutron dose; a neutron detection unit capable of detecting a second neutron dose of neutrons scattered inside an inspection object A by the emission of the neutrons from the neutron emission unit; a gamma-ray detection unit capable of detecting a gamma dose of gamma rays released from the inspection object A by the emission of the neutrons from the neutron emission unit; and an analysis unit configured to calculate a content of a predetermined substance based on the gamma dose and correct the content of the predetermined substance based on the first neutron dose and the second neutron dose.

The invention discloses a wide-range probe structure for gamma dose rate measurement, and relates to the technical field of radiation detection equipment, the probe structure is simple and reasonable in structure and convenient to install and use, three SiPin semiconductor devices with different areas are cut on a silicon wafer, and the probe structure with different sensitivities is realized. The measuring range of each SiPin semiconductor device measuring circuit of the pre-amplifier circuit is in four orders of magnitude, and SiPin semiconductor devices with different areas can be switched through an analog switch, so that the measuring range of the structure can work in eight orders of magnitude. On the basis that multiple measuring ranges can be obtained, the structure is small in overall size, low in cost and worthy of large-area popularization and application.

This application provides a situational fusion analysis method and system for nuclear radiation monitoring, relating to the field of data processing. In this method, a unified situational awareness session is constructed for nuclear radiation monitoring. Multi-node observation data is aligned using time window identifiers and spatial grid identifiers to form a grid observation package containing gamma dose rate, energy spectrum, nuclide activity concentration, and environmental information. Based on this, each situational node is driven to generate interpretative fragments such as propagation, shielding, background, and source terms. Candidate situational puzzles are assembled through complementary and coupling relationships, and verifiable traces are generated in reverse. By combining trace inquiry and cross-node evaluation to identify consistency illusions, multi-world situational branch construction is triggered, and private perturbation signatures are used to suppress the dominance of homogeneous nodes, thereby outputting a fusion result containing situational puzzles, evidence strength, and discrimination gaps. Implementing the technical solution provided in this application facilitates improved accuracy of situational fusion analysis in complex and atypical scenarios of nuclear radiation monitoring.

The invention discloses a wide-range gamma critical detector and a detection method, and the detector comprises a composite probe which carries out the region and critical radiation detection and self-inspection under the control of a signal processing system, and outputs a region signal and a critical signal corresponding to the region and critical gamma dose rate of an environment where the composite probe is located; the signal processing system is used for providing corresponding working voltage and self-checking control for the composite probe, performing data conversion and counting acquisition on the regional signal and the critical signal, and outputting a regional radiation detection result and a critical radiation detection result; and identifying and judging the critical radiation detection result based on a preset alarm threshold value, and selecting to output a corresponding alarm signal when the critical radiation detection result exceeds the alarm threshold value. According to the invention, the composite probe is utilized to detect the regional and critical radiation in the environment at the same time, the measurement range is widened, two alarm signals are selectively output according to the preset alarm threshold, the missing report rate and the false alarm rate of critical alarm are greatly reduced, the reliability and the stability are enhanced, and the alarm response speed is extremely high.

The invention discloses a neutron-gamma dosimeter based on double detectors and a gamma and neutron dose rate detection method, the neutron-gamma dosimeter comprises a gamma detector, a neutron-gamma detector and a processing module, the gamma detector can only respond to gamma rays and output signals, and the neutron-gamma dosimeter can only respond to the gamma rays and output signals. The neutron-gamma detector can respond to neutrons and gamma rays and output signals, and the processing module can receive the signals of the gamma detector and the neutron-gamma detector, determine the gamma dose rate based on the output signals of the gamma detector, and determine the dose rate of the neutron-gamma detector based on the difference value of the output signals of the gamma detector and the neutron-gamma detector. And determining the neutron dose rate. According to the invention, through combination of the gamma detector and the neutron gamma detector, simultaneous monitoring and dose separation of neutrons and gamma rays are realized, doses of two radiation types can be accurately measured and distinguished, and use requirements in various complex environments are met.

The invention relates to the field of gamma dose rate monitoring, and provides a gamma dose rate monitoring method and device based on eight SiPINs, and the method comprises the steps: collecting pulse signals outputted by eight SiPIN detectors, inputting the pulse signals into a self-adaptive time domain convolutional neural network of an index attenuation response function of the SiPIN detectors, and obtaining a stacked pulse feature vector; processing the stacked pulse feature vector by adopting a multi-path synchronous constraint loss function to obtain pulse arrival time, pulse amplitude and confidence coefficient parameters; constructing node features of the graph neural network based on the pulse arrival time, the pulse amplitude and the confidence coefficient parameter, and performing fusion calculation processing on the node features through the graph neural network to obtain a gamma dose rate measurement value; and comparing the gamma dose rate measurement value with a preset gamma dose rate threshold value, generating a corresponding monitoring state identifier according to a comparison result, and obtaining a gamma dose rate monitoring result. According to the invention, high-sensitivity real-time monitoring, dynamic pulse accumulation processing and grading state early warning of the gamma dose rate are realized.

The invention discloses a gamma dosage rate micro-dust sampling instrument which comprises a shell with an opening in the top, a filter membrane module, a sampling module, a detection module, a gas flow module, a data processing control module and a data display module, and the filter membrane module is arranged above the top of the shell and used for filtering radioactive micro-dust in gas to serve as a sample; the sampling module is arranged in the shell and below the filter membrane module, the sampling module comprises a sampling wind cup with an opening in the upper part, the sampling wind cup is correspondingly communicated with the filter membrane module, and an air guide pore plate is arranged at the opening of the sampling wind cup and is used for uniformly entering airflow; the detection module is arranged in the sampling wind cup and is used for measuring the gamma dosage rate instantaneous value of the sample; and the gas flow module is arranged in the shell and is communicated with the bottom of the sampling wind cup. The gamma dose rate micro-dust sampling instrument can be used as assembling equipment for individual soldiers, open air and shelters, and is used for sampling micro-dust in an atmospheric environment and a nuclear radioactive scene and detecting the gamma dose rate level of the radioactive scene in real time.

The invention discloses a wide-range weak current amplifier, device and method with leakage current measurement, and relates to the technical field of amplifiers and circuit devices. An input signal switching circuit of the amplifier is used for switching different amplifying circuits; the first amplifying circuit is used for amplifying an output signal and a leakage current signal of the high-pressure ionization chamber in a low measuring range; the second amplification circuit is used for amplifying output signals and leakage current signals of the high-pressure ionization chamber in the high-range and middle-range ranges and switching the output signals; the switching logic driving circuit is used for realizing logic driving of range switching and leakage current measurement; and the output signal processing circuit is used for carrying out switching selection, low-pass filtering and series matching processing on the output amplified signal. According to the invention, rapid and accurate switching among a high range, a middle range and a low range can be realized, and the accuracy of an actual gamma dose rate in a measurement environment is improved.

The utility model discloses a split type portable X-gamma dose rate instrument with positioning, and relates to the X-gamma dose rate instrument technical field, the X-gamma dose rate instrument comprises an RTK position indicator and an X-gamma dose rate instrument mechanism, the bottom surface of the RTK position indicator is provided with a holding mechanism, the holding mechanism comprises a threaded rod, the threaded rod is in threaded connection in the bottom surface of the RTK position indicator, and the X-gamma dose rate instrument mechanism is arranged in the holding mechanism. The bottom surface of the threaded rod is fixedly connected with a main rod, the top end of the outer surface of the main rod is fixedly connected with a side supporting plate, and the side supporting plate is movably connected to the bottom surface of the RTK positioning instrument. Through the cooperation of the fixing buckles, the buckles and the hanging belts, the device is obliquely arranged on one side of the body of a user in a straddling mode, the hands of the user can have a full rest conveniently when the user rushes to the road, and through the electrical connection between the secondary display screen and the main display screen, the user can conveniently and rapidly take a rest. The detection information of the X-gamma dose rate instrument can be transmitted to the interior of the main display screen, the position information of the X-gamma dose rate instrument can be detected through the RTK position indicator, and a battery is installed in the holding sleeve to supply power to the illuminating lamp.

The utility model discloses a gamma dose rate detector, which comprises a main machine shell, a driving device is arranged in the main machine shell, the driving end of the driving device is connected with a telescopic rod penetrating out of the main machine shell, the end part of the telescopic rod is provided with a detector, the surface of the detector is provided with a protection assembly, and the protection assembly comprises a pair of protection plates. A pair of protective plates are arranged on the surface of the detector, a pair of connecting plates are arranged on each protective plate, the protective plates sleeve the surface of the detector, the two connecting plates located on the horizontal plane are in threaded connection with hand screws, and through the structural design of the protective plates, the connecting plates, the hand screws, rubber protrusions and rubber pads, the detector can be protected; the detector is prevented from being collided and scraped by external objects when extending into a narrow area, abrasion of the detector is avoided, sensitive elements in the detector are protected to be intact, and accuracy of measured data and long-term stable operation of an instrument are ensured.

The utility model belongs to the technical field of neutron measurement, and particularly relates to a neutron dose rate measuring device based on a gamma energy spectrum. Comprising a shell, a high-voltage power supply, a photomultiplier, a protective cover and a lanthanum bromide crystal, the lanthanum bromide crystal and the photomultiplier are coupled and packaged in the protective cover, the photomultiplier is connected with the high-voltage power supply, and the protective cover and the high-voltage power supply are installed in the shell. The neutron dose rate measuring device has the advantages that the neutron dose rate can be directly measured, and the gamma dose rate can be measured at the same time. The system has the advantages of quick response, light weight, simplicity in operation, high applicability and the like, has the capability of measuring a conventional radiation environment and a nuclear accident emergency scene, can provide support for homemade autonomous controllability of radiation monitoring equipment, and provides a guidance basis for nuclear safety supervision and nuclear emergency actions of nuclear instruments.

The invention relates to the technical field of radioactivity measurement, in particular to radioactivity on-line monitoring of mineral products such as coal and iron ore, which comprises a radioactivity detection module for radioactivity on-line monitoring, an alarm output module when the radioactivity intensity of the mineral products exceeds the standard, and a measurement and control module for realizing measurement control, the radioactivity detection module is provided with a gamma ray detector; the radioactivity detection module is installed above a mineral product conveying line; the whole set of system is further provided with a positioning module to realize mineral product radioactive intensity standard exceeding positioning, and is provided with a nuclide identification module to realize nuclide type identification. A gamma dose equivalent rate module is configured to measure the dose equivalent rate; the problem that an existing online radioactivity monitoring system cannot be used for online radioactivity monitoring of mineral products is solved, and online radioactivity monitoring of the mineral products is achieved.

The invention relates to a gamma radiation field reconstruction method based on Gaussian puff model parameter assimilation. The method comprises the following steps: constructing a Gaussian puff model; based on a Gaussian puff model, obtaining an initial state vector of the puff when the puff passes through a preset position; on the basis of a Kalman filtering algorithm, under the condition that the plurality of puff passes through the preset position, updating the initial state vector at the preset position, and obtaining a target state vector for accumulating the plurality of puff at the preset position; through the target state vector, determining the total concentration of the superposed puff at the preset position after the plurality of puff passes; and based on the total concentration of the puff, determining a gamma dose rate at a preset position, and obtaining a gamma radiation field at the preset position. According to the method, the position of the puff is converted into the state vector, and the state vector of the puff is updated based on the Kalman filtering algorithm, so that the dynamic process of the puff changing along with time is obtained, real-time adjustment of the puff is better met, and the accuracy of the gamma radiation field is improved.

The present application provides a kind of nuclear power plant accident emergency air radiation monitoring method, comprising the following steps: step one: preliminary generation of radioactive plume diffusion situation based on diffusion model;Step two: radiation dose rate estimation on the axis of radioactive plume;Step three: intervention boundary estimation of 5 kinds of operation intervention level OIL;Step four: actual intervention boundary determination based on ground gamma dose rate inversion calculation;Step five: air radiation monitoring task area determination and division;Step six: air radiation monitoring task planning;Step seven: air radiation monitoring flight control.The method proposed by the present application can scientifically determine the nuclear radiation situation of nuclear power plant nuclear accident, and can accurately divide and assign the radiation monitoring area.The present application can realize the optimization of air nuclear radiation monitoring task planning, the optimal matching of radiation monitoring task and radiation monitoring equipment, and can effectively improve the operation efficiency of air nuclear radiation monitoring equipment, and meet the needs of air radiation monitoring task for auxiliary decision-making.

The present invention discloses a nuclear security inspection method and system based on drones, which relates to the field of radiation environment monitoring. The method includes the following steps: a drone formation conducts an inspection along a planned flight path; gamma dose rate and position data are collected and uploaded to a host computer for pre-processing, generating a three-dimensional point cloud map and performing visual analysis; a three-dimensional radiation anomaly hotspot search algorithm is used to identify gamma dose rate hotspots, perform preliminary positioning in three-dimensional space, and mark their coordinates and gamma dose rate values; the location of the preliminary determined radioactive source is sent to the drone, which scans and transmits the precise value to the host computer, where the precise location is determined using a nonlinear least squares method; the drone receives the position information, uses an onboard target re-identification system to locate a suspected target carrying a radioactive source, and issues a warning; the gamma dose rate information, position information, and target information are uploaded to a visual terminal interface to form trajectory information; and the above steps are repeated to locate radiation anomaly areas and suspicious targets. This invention provides efficient and accurate technical support for nuclear environmental safety.

The invention provides a device and method for positioning a gamma radiation source, and relates to the technical field of radiation monitoring. The device comprises a gamma dose rate instrument used for measuring the gamma radiation air absorption dose rate; the bracket is used for supporting and moving the gamma dose rate instrument, so that the gamma dose rate instrument can rotate in the horizontal direction; the shielding plate is arranged on the bracket, can coaxially rotate with the gamma dose rate instrument and is used for continuously shielding radiation on one side of the back of the gamma dose rate instrument; and the control module is used for acquiring measurement data of the gamma dose rate instrument and controlling the rotation angle of the bracket. According to the technical scheme, the target radioactive source can be positioned and the activity can be estimated at low cost.

The present invention belongs to the technical field of special safety facilities for nuclear power plants, and specifically relates to a method and a judgment module for preventing the accidental addition of drugs to a containment spray system of a nuclear power plant. The method is used for the opening permission logic of an injection valve of a chemical reagent adding box, and the chemical reagent adding box is used to inject a NaOH solution into a containment spray system in a containment. The opening permission logic of the injection valve is set to "'containment spray signal is turned on for 5 minutes' signal & 'high gamma dose rate of air in containment' signal & 'chemical reagent adding box non-low liquid level' signal". The present invention can ensure the containment spray action in the event of a secondary circuit breach in the containment, while avoiding a series of problems caused by unnecessary NaOH solution spraying, and can also ensure the containment spray action and NaOH solution spraying in the event of a coolant loss accident.

The invention relates to a gamma radiation dose rate instrument which comprises a handheld host end, a main grip, an electric telescopic rod and a pluggable probe. A first sensor cluster is mounted in the pluggable probe; and a second sensor cluster is accommodated in the inner cavity of the main grip. In the implementation process, the first gamma probe and the second gamma probe collect gamma dose initial data, temperature and humidity data and voltage data in an area where the first gamma probe and the second gamma probe are located when receiving a collection instruction, and the collected data are sent to the handheld host end; the handheld host end is used for controlling front-back stretching and retracting of the electric telescopic rod, rotation of the electric universal joint and releasing / retracting of the electric rope. The processor is also used for issuing acquisition instructions to the first gamma probe and the second gamma probe; and when the gamma dose initial data, the temperature and humidity data and the voltage data are received, compensating the gamma dose initial data based on the temperature and humidity data and the voltage data, and generating and displaying a gamma energy spectrum diagram according to the compensated gamma dose data.

The invention provides a gamma dose rate radiation monitor testing device and a use method thereof, the device comprises a cabinet body, a tool platform, a probe mechanism, a cleaning mechanism, a filtering circulation mechanism, a drying mechanism and a wiping mechanism, and a liftable loading platform is arranged on the working platform; the probe mechanism and the tool platform are oppositely arranged, and a plurality of liftable probe parts are arranged on the probe mechanism and are in contact with the corresponding test contacts for testing; the cleaning mechanism is provided with a liftable cleaning box, a plurality of guide holes corresponding to the positions of the probe parts are formed in the object carrying platform, and the probe parts penetrate through the guide holes and extend into the cleaning box for cleaning; the filtering and circulating mechanism is used for circularly filtering the cleaning liquid and flushing the cleaned probe part; the device can effectively remove pollutants, residual cleaning liquid and oxides on the surface of the probe part on line, test errors caused by smudginess of the probe are avoided, the service life of the probe is prolonged, and the detection efficiency and accuracy are improved.

The invention relates to a gamma radiation field reconstruction method based on Gaussian plume model parameter assimilation, and the method comprises the steps: constructing a Gaussian plume model, and determining a source item and a wind field parameter in the Gaussian plume model; determining an assimilation state variable according to the source item and the wind field parameter to obtain an assimilation vector value; correcting the assimilation vector value by adopting a three-dimensional variational assimilation method and taking a minimum objective function as an optimization objective, and determining a corrected assimilation vector value; performing dynamic correction and three-dimensional space reconstruction on the Gaussian smoke plume model based on the corrected assimilation vector value, and determining the pollutant correction concentration of the smoke plume at the preset position; and based on the pollutant correction concentration, determining a gamma dose rate at the preset position to obtain a gamma radiation field. The goals of performing data assimilation on key parameters, constructing an objective function by taking a real-time environment gamma dose rate observation value as a constraint condition based on a three-dimensional variational assimilation method, and performing dynamic correction and three-dimensional space reconstruction on the Gaussian plume model output radiation field are achieved.

The application discloses a BNCT gamma dose measurement system based on sCVD diamond, wherein a sCVD diamond detector signal is transmitted to a radio frequency amplifier for conditioning and amplification, the amplified analog signal is converted into a digital signal by a high-speed ADC and is transmitted to an FPGA for processing, a trigger threshold is set to obtain effective radiation signals, and each radiation signal data point is collected; waveform data collected by the ADC is transmitted to an upper computer, discrimination of gamma signals and acquisition of air absorption dose data are completed in the upper computer, firstly, the radiation signals are subjected to filtering and normalization processing; secondly, the processed radiation signals are input into a neutron-gamma discrimination program for processing, and the radiation signals in the discrimination results are input into an air absorption dose conversion program to obtain final gamma dose information. The application integrates the functions of a diamond detector, an ADC and an FPGA, cooperates with modularized design of each part, so that the detection method can realize real-time collection in a high-dose-rate neutron gamma mixed field, can effectively discriminate gamma signals and can obtain a gamma dose rate, and has high practicability.

The invention discloses a calculation model of a complex gamma dose field radioactive source, aiming at the problem that the contribution of a body source and a line source is difficult to distinguish in the existing monitoring, a natural background, a uniform dispersion body source and a leakage channel line source are simultaneously incorporated into a gamma dose rate measurement model in a cuboid space; establishing a body source volume fraction and line source line integral dose formula according to nuclide activity, a kerma constant and geometric parameters; 2 or more measuring points are arranged to construct a linear equation set, MCNP5 Monte Carlo simulation is used for optimizing the size, the position and the direction of the lead shielding body, equation morbidity is reduced, and contribution of each source item is obtained through solving. The experimental verification deviation is less than 33%, and reliable technical support can be provided for radiation source discrimination and protection after nuclear power station and nuclear facility accidents.