25 results about "Gamma dose" patented technology

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.

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.

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 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 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 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.

The invention relates to a nuclear accident environment gamma radiation field reconstruction method based on same variable assimilation, and the method comprises the steps: constructing an initial gamma dose rate field numerical calculation model, carrying out the grid scale division of a three-dimensional space region, and determining a gamma dose rate obtained through calculation at a grid point as a background state variable; acquiring real-time environment gamma dose rate data of a plurality of observation station positions, and constructing an observation vector; based on the background state variable and the observation vector, constructing a mapping relation between a model space and an observation space, and determining an observation operator; a three-dimensional variational assimilation method is adopted, target function minimization is used as an optimization target, assimilation correction is carried out on the basis of background state variables, and assimilation state variable solutions are obtained. By constructing the dose rate field model, the gamma dose rate is directly used as an assimilation variable, subsequent parameter conversion is not needed, and the purposes of assimilating the gamma dose rate, directly correcting the gamma dose rate, obtaining a theoretical optimal solution of the gamma dose rate and improving the accuracy of gamma radiation field construction are achieved.

The application discloses a method, device and equipment for determining a background value of radium-226 and a storage medium. The application obtains an environmental radiation gamma dose rate monitoring point; monitors the environmental radiation gamma dose rate to obtain environmental radiation gamma dose rate monitoring data and performs outlier processing to obtain a qualified monitoring point of the environmental radiation gamma dose rate; determines a radium-226 monitoring point based on the qualified monitoring point of the environmental radiation gamma dose rate and performs sampling based on the radium-226 monitoring point; monitors the activity concentration of radium-226 based on a radium-226 sampling result to obtain radium-226 activity concentration monitoring data; performs outlier processing on the radium-226 activity concentration monitoring data to determine the background value of radium-226 in soil, and the radium-226 monitoring point is quickly and accurately determined through screening of the gamma dose rate, and the background value of soil radium-226 is accurately determined according to the radium-226 monitoring point.

The invention discloses an improved Transform-based source item inversion method and system and a storage medium, and the method comprises the steps: obtaining a training data set which comprises a plurality of groups of training samples, and each group of training samples comprises source item data, gamma dose rate time sequence data and corresponding meteorological data; performing Gamma angle field conversion on the gamma dose rate time sequence data, and performing normalization processing on the meteorological data; constructing a source item inversion model, the input data of the source item inversion model being gamma dose rate time sequence data and corresponding meteorological data, and the output data being source item data obtained by inversion; processing the dose rate shallow layer features through a self-attention sub-network to obtain dose rate deep layer features; fusing the dose rate deep layer features and the meteorological shallow layer features through a feature fusion sub-network, and inputting the fused features into a second multi-layer perceptron for training to obtain a source item inversion model; and carrying out source item inversion by adopting the source item inversion model.

The invention relates to the field of gamma dose rate monitoring, and provides a high-sensitivity fast-response low-energy gamma dose rate monitoring method and device, and the method comprises the steps: collecting and grading gamma ray pulse signals, and obtaining a pulse arrival time interval sequence and multi-threshold counting rate data; statistical characteristics are extracted, a mixed prior constraint model is constructed for variational coding, potential distribution parameters are obtained and decoded, and statistical enhanced counting rate data are obtained; fusing the multi-threshold counting rate data and the statistical enhancement counting rate data to obtain fused counting rate data, performing feature extraction, obtaining energy section feature data, performing calculation, obtaining time sequence association intensity, and performing processing through a multi-nuclide spectrum unfolding algorithm to obtain nuclide component data; and monitoring the electric quantity of the equipment battery, performing precision optimization processing on the nuclide component data, converting the nuclide component data into a gamma dose rate value, and outputting gamma dose rate data. According to the invention, real-time monitoring of low-energy gamma rays, nuclide component identification and low-power consumption dose rate measurement are realized.

The invention discloses a neutron capture therapy device based on a DT tube, and the device comprises a beam shaping system, the interior of the beam shaping system is provided with a moderator, the moderator is composed of a mixture of aluminum fluoride and metal aluminum, and the preferable mass ratio is 40: 60. The beam shaping system further comprises a reflector arranged on the periphery of the moderator, a thermal neutron filter located at the downstream of the beam, a collimator at the emitting end and a shielding body used for restraining gamma rays, and an integrated structure for moderating, filtering and collimating 14 MeV fast neutrons generated by the DT tube is formed. The invention relates to the technical field of BNCT treatment equipment. Through cooperation of the composite moderator and structure optimization, the thermal neutron flux is remarkably reduced, the epithermal neutron flux is improved, the superthermal / thermal flux ratio of the emergent beam is remarkably improved, the fast neutron and gamma dose is effectively controlled, the IAEA recommended standard is met, and the method is suitable for miniaturization, popularization and application of compact clinical BNCT equipment.

The application discloses a kind of real-time high-precision radiation environment monitoring instrument based on autoregressive encoder, including data acquisition module and host computer;The data acquisition module includes gamma dose rate sensor, temperature sensor and humidity sensor;Data acquisition module and host computer are sequentially connected.The host computer includes data processing module, real-time prediction module, data storage unit and result display module.The real-time high-precision radiation environment monitoring instrument based on the regression encoder disclosed in the application has the advantages of strong real-time, high prediction accuracy.

This invention discloses an online dose monitoring and alarm system and method for boron neutron capture therapy, belonging to the field of radiation dose monitoring technology. It includes at least one set of integrated wireless monitoring probes and a central monitoring platform. The system highly integrates a radiation detection module, a photoelectric conversion module, a high-speed analog-to-digital / digital-to-analog conversion module, an FPGA module, a wireless communication module, and a built-in lithium battery. The FPGA executes a shape discrimination algorithm based on the difference between pulse rise time and / or decay time at the probe end using hardware logic to distinguish neutron / gamma events and calculate the count rate and dose rate in real time. When the monitored value exceeds a preset safety threshold, the high-speed digital-to-analog conversion module drives an LED indicator and / or a buzzer to issue a local audible and visual alarm. Compared with existing technologies, this invention achieves synchronous real-time monitoring of neutron flux and gamma dose, improves alarm response speed, facilitates flexible deployment near the treatment head or patient irradiation field in space-constrained locations, and enhances the safety and accuracy of treatment.

The application discloses a numerical simulation method and device for predicting mechanical performance degradation of concrete under gamma irradiation, converts a gamma irradiation dose field into a shrinkage load accumulated with time, and only applies the shrinkage load to a mortar matrix in a three-dimensional mesoscopic model of concrete, so as to realize fine simulation of mortar shrinkage, interface stress concentration and damage evolution under long-term gamma irradiation. By using the technical scheme of the application, the technical problems that the existing method is difficult to consider gamma dose spatial attenuation and mortar shrinkage are solved.

The application discloses a kind of boron neutron capture therapy beam gamma dose measurement methods, it is related to radiotherapy technical field, first thermoluminescence dosimeter is standardized annealing pretreatment, and screening, numbering;Positioning and calibration are carried out to water equivalent phantom fixed on treatment bed, complete reference positioning;Thermoluminescence dosimeter is loaded in water equivalent phantom and is irradiated again;After irradiation, take out phantom, establish the one-to-one correspondence between unique number and its three-dimensional space position in phantom, and record;First measurement and second measurement are carried out to all dosimeters in turn, calculate thermoluminescence net gamma count, obtain absorbed dose value;Thermoluminescence dosimeter is annealed again, for subsequent circulation use conveniently.The application in the application multiple thermoluminescence dosimeters are irradiated simultaneously, shorten time;Two independent measurements, deduct interference signal;Complex operation process standardization, programming, improve measurement repeatability and efficiency, convenient, novel, accurate.

The application discloses a nuclear power plant pressure vessel radioactive detection device, equipment and method. The device is used for source term investigation of an old top cover of a pressure vessel and comprises a gamma energy spectrum measurement module, a gamma dose rate measurement module and a loading module. The gamma energy spectrum measurement module and the gamma dose rate measurement module are arranged on the loading module. The loading module is provided with a loading driving element and a driving wheel. The loading driving element and the driving wheel are in transmission connection to drive the driving wheel to rotate and drive the loading module to move, so that the gamma energy spectrum measurement module can be moved to the spherical center of the old top cover and detect the old top cover. The device can move the gamma energy spectrum measurement module to the spherical center of the old top cover, ensure that the distance between the detector center and each region of the inner surface of the top cover is the same, thereby reducing the error of source term detection of the old top cover and improving the accuracy of source term detection of the old top cover.

The invention relates to the technical field of generation, regulation and control of a composite radiation environment, in particular to a generation method of a composite radiation environment for circuit damage effect research. The method comprises the following steps: S1, preparing three shielding boxes, namely a single-layer aluminum shielding box and a double-layer aluminum shielding box of which the front ends are coated with polytetrafluoroethylene, and a lead-aluminum shielding box of which the front part is coated with lead glass and which is sequentially arranged from outside to inside; s2, placing the three shielding boxes in a target chamber of a kilofocal laser device, and connecting signal receiving antennas inside and outside the shielding boxes; s3, generating electromagnetic pulse and gamma radiation through interaction of the picosecond laser and the solid target, and forming a composite radiation environment after separation and regulation of a shielding box; and S4, connecting a magnetic field antenna and an attenuator to an oscilloscope through a cable to collect electromagnetic pulse signals, and testing gamma radiation intensity through a gamma dose piece. According to the scheme, the technical problems that most existing composite radiation environment generation methods are complex in equipment, high in cost and the like, and the requirements of scientific research and engineering application are difficult to meet can be solved.