207 results about "Nuclear radiation" patented technology

The invention relates to the technical field of nuclear radiation imaging, in particular to a radiation array detector, a back scattering imaging system and a back scattering imaging method. The radiation array detector comprises an X-ray photon absorption structure which comprises high-strip-shaped scintillators and low-strip-shaped scintillators which are alternately arranged, the high-strip-shaped scintillators are used for detecting back scattering X-ray photons incident at all angles, the low-strip-shaped scintillators are used for accurately determining the incident direction of the X-ray photons through the collimation effect, and the high-strip-shaped scintillators and the low-strip-shaped scintillators are used for detecting the incident direction of the back scattering X-ray photons; after X-rays enter the photon absorption structure, the high-strip-shaped scintillators and / or the low-strip-shaped scintillators receiving X-ray photons generate scintillation photons. The silicon photomultiplier array is connected with the high strip-shaped scintillator and the low strip-shaped scintillator through a light guide and is used for converting scintillation photons into photoelectric signals; and the position and energy information coding circuit is used for carrying out position and energy information coding on the photoelectric signals generated by the silicon photomultiplier array. According to the invention, the detection efficiency and the direction identification capability of the back scattering X-ray can be effectively improved.

The invention discloses a convolutional neural network and multi-source data fusion-based nuclear radiation on-line monitoring method, which comprises the following steps of: acquiring laser radar point cloud data, a radiation dose rate and a radiation image of a monitoring area by adopting an unmanned aerial vehicle, and de-noising the radiation image by adopting a double-branch convolutional neural network; determining the track position of the unmanned aerial vehicle according to the laser radar point cloud and the de-noised image; performing space-time registration on the radiation dose rate and the track position of the unmanned aerial vehicle to form a data set, and obtaining a continuous radiation field of the monitoring area by adopting Kriging interpolation; according to the continuous radiation field, an L-BFGS-B algorithm is adopted to carry out minimization solution on a loss function with the radiation source position as an optimization variable, and position coordinates of the radiation source are obtained; performing data cleaning on the radiation dose in the continuous radiation field, and then performing multi-dimensional feature extraction to obtain a feature vector; and inputting the feature vectors into a plurality of prediction models to obtain a plurality of predicted radiation doses, and carrying out weighted fusion to obtain a predicted dose rate of the radiation source.

The invention discloses a nuclear radiation energy spectrum double-domain collaborative optimization method and a related device, and belongs to the technical field of nuclear radiation measurement, and the method comprises the steps: obtaining an original distortion pulse sequence generated by nuclear radiation measurement; a double-domain collaborative energy spectrum optimization model is constructed, the double-domain collaborative energy spectrum optimization model comprises a pulse domain repair model and an energy spectrum domain reconstruction model which are arranged in parallel, and the pulse domain repair model is used for performing pulse-by-pulse repair on the amplitude and the arrival time of the original distorted pulse sequence and outputting a repaired pulse sequence; the energy spectrum domain reconstruction model is used for converting the repaired pulse sequence into an energy spectrum diagram; in the training process of the double-domain collaborative energy spectrum optimization model, the pulse domain repair model and the energy spectrum domain reconstruction model share the back propagation gradient of the joint loss function, so that bidirectional closed-loop collaborative optimization of the pulse repair model and the energy spectrum reconstruction model can be realized, the problem of step-by-step error amplification caused by a traditional serial processing mode is avoided, and the performance of the system is improved. And the authenticity and the accuracy of the output energy spectrum are obviously improved.

The invention discloses a nuclear accident dynamic safe operation time assessment method and system based on data fusion, relates to the technical field of nuclear radiation protection, and solves the technical problems that the safe operation time is not accurate enough and dynamic dose assessment is difficult in nuclear accident emergency response. According to the technical scheme, nuclear accident prediction data and site real-time monitoring data are fused, a data assimilation fusion algorithm and an intelligent analysis model are combined, the radiation dose and environmental conditions of an accident site are comprehensively evaluated, and safety operation time and risk levels of different areas are dynamically calculated and updated; by considering the building shielding effect and supporting the federated learning framework, the cooperative evaluation of multiple monitoring points is realized, so that the operation time evaluation precision and decision-making efficiency in the nuclear accident emergency response are greatly improved. Finally, operation suggestions can be fed back and updated in real time, and the real-time performance and accuracy of emergency command decisions are ensured.

The invention provides a three-dimensional reconstruction method and system in a nuclear irradiation environment, and relates to the technical field of computer vision. According to the method, a Swin Transformer network is adopted to perform feature extraction processing on an original image containing radiation noise, a constructed three-dimensional reconstruction network adopts a U-Net architecture, reservation of detail features is ensured through an encoding-decoding process, after radiation noise processing is completed, an FFB6D network is introduced to directly process a nuclear radiation environment reconstruction image, and the method has the advantages that the method is simple and convenient to operate and high in practicability. The accuracy and the stability of pose estimation under severe visual conditions are improved, and a geometric basis is provided for three-dimensional reconstruction. Model selection and optimization are carried out on all the modules adopted by the system according to the characteristics of the nuclear irradiation environment, technical resultant force is formed, a high-performance and full-automatic three-dimensional reconstruction system specially designed for the extremely severe visual environment such as nuclear irradiation is finally constructed, and the precision, robustness and practicability of three-dimensional perception in the field are remarkably improved.

This invention relates to the field of nuclear radiation detection technology, and more particularly to an energy spectrum processing method for a quasi-hemispherical CdZnTe detector. The method includes: acquiring the raw signal collected by the quasi-hemispherical CdZnTe detector; normalizing the amplitude of the raw signal from the baseline to the highest point during the rise phase; dynamically selecting multiple energy thresholds; performing rise time discrimination on the normalized signal within each energy threshold; filtering out signals with rise times greater than RTflag and determining the rise time range corresponding to that energy threshold; constructing an intermediate energy spectrum corresponding to each energy threshold based on the signals with rise times greater than RTflag and the rise time range; and post-processing the intermediate energy spectrum to obtain the target energy spectrum corresponding to each energy threshold. This invention combines energy threshold discrimination, rise time discrimination, and energy spectrum post-processing algorithms to stably improve the energy resolution of the quasi-hemispherical CdZnTe detector for 662 keV gamma rays from the conventional 2%~3% to less than 1%.

The application discloses a double-gas-chamber neutron detector, belonging to the technical field of nuclear radiation detection and particle detection, comprising a gadolinium film neutron conversion layer, two time projection chamber (TPC) modules and an optional energy quantifier module. After capturing thermal neutrons, the gadolinium film generates multi-state particles, and the two TPC modules realize 4π solid angle neutron detection through electronic signal coincidence. The application replaces the scarce 3 He with gadolinium, combines the track reconstruction capability of the double TPC module, significantly improves the neutron detection efficiency and signal-to-noise ratio, and is suitable for nuclear reactor monitoring, industrial material analysis, agricultural moisture detection and deep space exploration and other fields. Through electronic-gamma coincidence measurement and mode recognition, high-precision neutron signal reconstruction and environmental background suppression are realized.

The application provides a flame-retardant composite shielding material and a preparation method and application thereof, and belongs to the technical field of nuclear radiation shielding materials. The flame-retardant composite shielding material comprises the following components in parts by mass: 10-20 parts of high-density polyethylene, 68-81 parts of lead, 0.5-4 parts of boron carbide and 9-20 parts of a flame retardant. By adopting high-density polyethylene, lead, boron carbide and a flame retardant and controlling the mass fraction of each component, the heat resistance, flame retardance and shielding performance of the flame-retardant composite shielding material can be improved.

This invention relates to the fields of nuclear detection electronics and radiation signal processing technology, specifically to an intelligent analysis system and method for nuclear radiation data. The system includes: acquiring a discrete voltage sequence output by the detector; marking pulse signals as clean pulses and calculating the real-time decay constant; calculating the net signal amplitude using a digital twin state-space recursive model; determining the real-time count rate based on the net signal amplitude and calculating the dynamic time window width based on the real-time count rate; discretely accumulating the net signal amplitude based on the dynamic time window width to generate a single-particle physical energy value; determining the measured peak position based on the single-particle physical energy value and generating a gain adjustment coefficient by combining the measured peak position with the real-time decay constant; and outputting a gain control signal based on the gain adjustment coefficient. This invention ensures precise synchronization between the subsequent calculation model and the current physical state of the detector, thereby significantly improving the physical authenticity and accuracy of energy spectrum analysis under varying temperature conditions.

A self-powered nuclear radiation detector. The self-powered nuclear radiation detector includes a cable assembly, a temperature compensation assembly, and a metallic outer sheath. The cable assembly includes a metallic signal lead, an insulative material surrounding the metallic signal lead, and a metallic sheath surrounding the insulative material. The temperature compensation assembly includes a second metallic signal lead, a second insulative material surrounding the second metallic signal lead, and a second metallic sheath surrounding the second insulative material. The metallic outer sheath surrounds the cable assembly and the temperature compensation assembly.

The invention relates to a sub-pixel positioning method and device for a nuclear radiation detector and the nuclear radiation detector. The method comprises the following steps: in the process of detecting photons by a detector, acquiring a detection signal which is excited by the photons colliding with a detection crystal and is collected by at least one physical pixel; determining signal description data of the corresponding detection signals according to the detection signals of different physical pixels; based on the trained sub-pixel positioning model, according to the signal description data, determining the impact position of the photons in the detector; the impact position is any sub-pixel position relative to the center of the target physical pixel; the target physical pixel is the physical pixel with the strongest detection signal. According to the method, the detection signal excited by the photon impact event is collected, the signal description data is extracted, and the sub-pixel level position information is effectively captured by using the sub-pixel positioning model, so that the accurate sub-pixel impact position of the photon relative to the pixel center with the strongest signal intensity is deduced, and the reliability of sub-pixel positioning is remarkably improved.

The application discloses a current source module capable of simulating output current of an ionization chamber and a nuclear radiation monitoring device, and the current source module comprises an interface unit, a program-controlled switch unit, a V-I conversion unit, a 2N-way DAC, a control unit and a power supply unit which are sequentially connected. The 2N-way DAC outputs multiple voltage signals, then the voltage signals are converted into current signals by the V-I conversion unit, the current signals can enter a preprocessor after the program-controlled switch and the interface, and the control unit can control the size of the voltage signal output by each channel of the DAC and the closing of the program-controlled switch, so that the size of the output current and the control of the direct current or pulse current are realized. The application can simulate the current generated by the ionization chamber in a gamma radiation field, and realizes the detection and result evaluation of the nuclear radiation monitoring device which is composed of the ionization chamber and the preprocessor and cannot be disassembled.

An X-ray scanning system includes: a housing configured to be handheld; an X-ray source for scanning a target; a set of first detectors configured to be mechanically coupled to the housing and to detect resulting X-rays received from the target responsive to scanning the target; a second detector configured to be mechanically coupled to the housing; and a set of processors mechanically coupled to the housing and communicatively linked to the first detector and to the second detector so as to receive first and second signals, respectively, therefrom. The processor(s) are configured to: generate an image of the target based on the first signal; distinguish, in the second signal, a contribution of passive nuclear radiation detected at the second detector; and provide an output corresponding to the contribution of passive nuclear radiation. A related system for identifying a radioactive isotope, along with corresponding methods, are provided.

The invention discloses a passive nucleon level gage and a level output control method and a monitoring system thereof in a nuclear radiation flaw detection period. The level output method comprises the following steps: judging that nuclear radiation flaw detection interference exists in a measurement environment in which the passive nucleon level gage is positioned; executing at least one of the following output guarantee operations: setting an output switch of the passive nucleon level gage to be in a preset guarantee state, wherein the preset guarantee state is a switch-on state or a switch-off state; or the output switch of the passive nucleon level gage is maintained in the on-off state before it is judged that nuclear radiation flaw detection interference exists; or the normal material level value of the passive nucleon level gauge is replaced with the alternative material level value, or the on-off state of an output switch of the passive nucleon level gauge is determined based on the alternative material level value, and the alternative material level value is used for replacing the normal material level value when flaw detection interference is detected. The normal material level value is a material level value generated on the basis of the real-time measurement data in the state that the guarantee operation is not executed. The device realizes material level output guarantee control during nuclear radiation flaw detection.

This invention relates to the field of nuclear radiation detection technology and discloses a two-dimensional array detector for measuring the spatial distribution of neutrons and photons. The detector body includes a detector body comprising a detection unit layer, a light guide layer, and a readout layer. The detection unit layer, light guide layer, and readout layer are vertically stacked sequentially from top to bottom to form a three-layer modular integrated structure. The layers are precisely mechanically aligned and optically coupled without air gaps. The light guide layer is composed of an array of multiple optical fibers. The detection unit layer is composed of an array of multiple detection units, with each detection unit corresponding to one optical fiber. This invention offers advantages such as modularity, high spatial resolution, and real-time signal processing. It can be applied to the measurement of the spatial distribution of neutrons and photons in the field of boron neutron capture therapy, meeting the practical needs of online real-time measurement of the spatial distribution of the neutron-photon mixed radiation field and accurate verification of the treatment irradiation field dose in boron neutron capture therapy.

The invention discloses a multi-legged robot radiation source autonomous positioning method based on AI dynamic path optimization, and belongs to the technical field of nuclear radiation monitoring and intelligent robots, and the method comprises the steps: collecting space radiation intensity data, eliminating pseudo sources, calculating a radiation gradient field, and constructing a radiation field in real time; an improved social network search algorithm is adopted to solve a target function of an optimal path, the target function dynamically fuses a path length and a radiation gradient integral, and a path weight coefficient alpha and a radiation weight coefficient beta are adjusted in real time through a Sigmoid function according to environmental complexity; the multi-legged robot conducts gait self-adaptive control according to the optimal path, and the movement speed is adjusted according to the real-time radiation intensity. According to the method, dynamic path optimization, multi-mode perception and pseudo source elimination are fused, the problems of path disjunction, data distortion, pseudo source interference, insufficient dynamic adaptability and the like in the prior art are solved, and an autonomous and credible radiation source positioning solution is provided for nuclear leakage emergency.

The application discloses a system and a method for accelerating the degradation of solid nuclear waste, aiming at eliminating radioactive hazards from the root. The system comprises an inner barrier, an intermediate filling layer and an outer barrier. The inner barrier is made of functional parallel nanotube material, the outer barrier is a titanium alloy container, and the intermediate filling layer is nanotube grade graphene powder. The method is to wrap the solid nuclear waste in the inner barrier, assemble it through the intermediate filling layer and the outer barrier, and then store it in a deep geological environment. Through the strong parallel force field created by the inner barrier and the parallel wave particle flow in the environment, the energy is gathered to deconstruct the cross superposition operation state of the basic particles of the nuclear radiation source. The scheme combines advanced material science, photon physics and philosophical thought, realizes the complete elimination of radioactive hazards, provides the possibility for the transformation and reuse of solid nuclear waste, and has environmental protection and innovation.

The invention provides a double-layer crucible. The double-layer crucible comprises an outer circular tube-shaped container, an inner circular tube-shaped container and a T-shaped cylindrical plug, the double-layer structure can solve the problems of raw material loss and proportion imbalance caused in the process of filling the raw materials into the crucible, and the perovskite crystal which can be used for normal-temperature nuclear radiation detection can be industrially prepared by using the Bridgman method in an economic mode. And a vacuum cavity can be provided as a temperature buffer area, so that the thermal disturbance of a crystal growth interface is reduced. The method can also be used for atmosphere regulation and control, and component segregation caused by element volatilization is relieved. The invention also provides a method for preparing a perovskite polycrystal material and a method for preparing a perovskite single crystal.

The invention provides a sub-noise solid argon detector data trigger acquisition method, system and device based on wavelet conversion reconstruction, and relates to the technical field of nuclear radiation detection and data processing. The system effectively reduces the false triggering rate, improves the collection efficiency of effective signals, improves the detection sensitivity of weak nuclear signals, is simple in structure, is easy to achieve, and has a good application prospect.

The invention discloses a single-layer Compton camera system and an imaging method, and relates to the technical field of nuclear radiation imaging. The system comprises a single-plane pixel type gamma ray detector used for collecting gamma ray interaction event data, including time information and energy information of each interaction and two-dimensional position information in a detector plane, and forming pixel counting distribution; the shielding structure is arranged on one side of the plane of the detector, is located in a local area of the detector and is used for enabling pixel counting distribution to generate a local counting missing feature when gamma rays are incident from one side where the shielding structure is located; and the judging and imaging module is used for judging a gamma ray incident side based on the local counting missing feature and executing Compton imaging reconstruction in a corresponding hemispherical view field range according to the judged incident side. According to the invention, partitioned omnidirectional imaging can be carried out on the radioactive source under the condition that a detector does not need to act on depth information, and meanwhile, generation of mirror image artifacts is avoided.

The application relates to a long-service-life anti-nuclear-radiation dustproof magnetic liquid sealing device, and belongs to the technical field of mechanical engineering sealing. The device comprises a shell assembly, a threaded end cover, a clamping hoop assembly, a magnetic guide sleeve assembly, magnetic liquid, four permanent magnets, four magnetic shielding rings, a right bearing, a right pole shoe assembly, a middle pole shoe assembly, a left pole shoe assembly, a left bearing and a syringe. The magnetic liquid is injected between the permanent magnet I, the permanent magnet IV and the shell to form a magnetic liquid static seal, and the magnetic liquid is injected between the permanent magnet I and the permanent magnet IV and the magnetic guide sleeve to form a magnetic liquid dynamic seal, so that the right bearing and the left bearing are prevented from being blocked due to the entry of radioactive powder, and the stable operation of the device is ensured; when the original magnetic liquid is consumed, the locking screw on the shell is taken out, the magnetic liquid is injected into the opened magnetic liquid supplement injection channel through the syringe, under the action of the magnetic field, the injected magnetic liquid re-forms the magnetic liquid seal, the complexity of the maintenance operation is reduced, and the pressure resistance of the device is ensured.

The invention relates to a nuclear radiation detection system based on a plug-in detector, and the system comprises a detector plug-in and a mobile terminal. Wherein the detector plug-in comprises a ray detection unit, a temperature detection unit and a control module, and the ray detection unit and the temperature detection unit are both connected with the control module; the ray detection unit is used for acquiring a radiation analog signal; the temperature detection unit is used for collecting a temperature digital signal corresponding to the radiation analog signal; the control module is connected with the mobile terminal and is used for converting the radiation analog signal into corresponding energy spectrum data and transmitting the energy spectrum data and the temperature digital signal to the mobile terminal; and the mobile terminal is used for determining the radiation dose corresponding to the energy spectrum data and correcting the radiation dose according to the temperature digital signal. According to the invention, the problem that the accurate nuclear radiation dose information cannot be conveniently obtained is solved, the accurate nuclear radiation dose information can be conveniently obtained, and the portability of the detection system and the accuracy of the detection data are improved.

The invention relates to a gamma ray source identification and imaging instrument and a gamma ray imaging system, and belongs to the technical field of nuclear radiation detection and imaging. The gamma ray source identification and imaging instrument comprises a shell and a gamma detector module arranged in the shell, wherein the gamma detector module comprises a scattering detector and an absorption detector which are sequentially arranged along a preset direction; each of the scattering detector and the absorption detector comprises a crystal array and a photoelectric detector array; and the gamma ray source identification and imaging instrument is configured to transmit a radiation detection signal obtained by the gamma detector module to the upper computer so as to display a radiation energy spectrum and a radiation image. According to the gamma ray source identification and imaging instrument, collimation of the gamma ray direction can be achieved without a heavy mechanical collimator, the gamma ray source identification and imaging instrument has the gamma ray source nuclide identification and space positioning capacity, high-sensitivity imaging can be achieved, and the gamma ray source identification and imaging instrument has the advantages of being compact, small, exquisite and portable.

The invention relates to the technical field of nuclear radiation detection, in particular to a portable pulse X-ray dose rate meter and a detection method. The probe module is used for simultaneously acquiring dose information and time information of pulse X-rays; the circuit processing module is connected with the probe module and used for collecting and processing probe signals; and the host module is in communication connection with the circuit processing module and is used for setting parameters, receiving data, analyzing dosage and outputting a detection result dosage value. The invention designs a portable pulse X-ray dose rate instrument, which can measure a pulse X-ray dose rate value with short pulse time and high instantaneous dose rate in a radiation field, meet the calibration requirement of a nuclear critical accident alarm system, ensure the safety of facilities and personnel and promote the research and development of working measuring instruments.

A nuclear-grade radiation-resistant infrared video monitoring system belongs to the technical field of nuclear facility safety monitoring, and comprises a radiation-resistant infrared camera used for collecting infrared video data in a strong nuclear radiation environment; the image processing unit is used for performing enhancement processing on the infrared video data, removing non-uniform fixed mode noise caused by radiation and obtaining an enhanced video image; and the intelligent analysis and prediction unit is used for carrying out quantitative identification on the enhanced video image, obtaining pipeline defects in the video image and carrying out risk prediction. The problems that no available infrared monitoring equipment exists in a radiation area of an existing nuclear facility, the existing nuclear facility depends on an imported visible light camera (the problems of short service life, sensitivity to temperature, poor image quality and the like), and the existing nuclear facility lacks intelligent early warning capability are solved.

This invention provides an online monitoring system and method for krypton-85 based on a scintillation fiber bundle, specifically relating to the field of nuclear radiation monitoring. The online monitoring system includes: a gas pretreatment unit, a detection unit, an electronics and data acquisition unit, and a control unit. The detection unit is connected to the gas output terminal of the gas pretreatment unit. The detection unit includes a detection chamber, a scintillation fiber bundle, a first photomultiplier tube, a second photomultiplier tube, and a lead shield. The scintillation fiber bundle is disposed within the detection chamber, and the first and second photomultiplier tubes are respectively located at both ends of the detection chamber, with their photosensitive surfaces optically coupled to both ends of the scintillation fiber bundle. The lead shield covers the outside of the detection chamber. The electronics and data acquisition unit receives the output signal from the detection unit, and the control unit controls the automatic operation of the entire system, parameter setting, and data acquisition and processing. This invention solves the problems of poor timeliness and insufficient representativeness in traditional offline monitoring methods.

The application provides a kind of intelligent distribution linkage cabinet control method and system for nuclear radiation control area, the method includes: receiving the operation request initiated by user on distribution equipment, by other means, complete user identity authentication and real-time check of nuclear power plant control area access authority;Judge its personnel type, and according to the first preset rule corresponding to personnel type, verify the validity of its radiation work permit and the matching of operation area and current control area entrance;Personal dosimeter is allocated and activated for user, and the unique identification of the dosimeter, user identity information and a specified locker establish logical binding relationship, when it is confirmed by hardware sensing that it has been taken away by user, send unlock instruction;When user initiates return operation and passes identity review, unlock the bound locker, and remove the binding relationship.The application can realize the systematic leap of nuclear radiation control area access management in safety, efficiency and intelligent level.

The invention discloses a nuclear biochemical monitoring system and method, the system comprises a nuclear radiation detection module, a chemical toxic agent detection module, a biological factor detection module, an intelligent central control unit, a monitoring terminal and a remote command platform, the nuclear radiation detection module adopts a Geiger tube sensor to detect alpha, beta, neutron and gamma rays; the chemical toxic agent detection module is used for detecting various chemical toxic agents based on an ion mobility spectrometry technology; the biological factor detection module adopts an investigation, acquisition and detection integrated system to monitor and preliminarily screen biological aerosol, the intelligent central control unit processes, studies and judges multi-source data through 5G / Beidou communication by using a data fusion algorithm, and the monitoring terminal receives and prompts a monitoring report and a disposal scheme. The remote command platform realizes data visualization, long-term storage, multi-path alarm and emergency disposal scheme generation and issuing; according to the invention, real-time, rapid and cooperative monitoring and intelligent grading response of nuclear, biological and chemical threat factors are realized.

The invention belongs to the technical field of nuclear radiation protection, and particularly relates to an advanced fast reactor special alpha nuclide human body protection filter box and a protection device. A tank cover is connected with the upper end of a tank body, a rubber pad is arranged in the tank cover, the tank cover and the tank body are externally connected through a connecting rope, a special alpha nuclide filtering unit is arranged in the tank body, air particle filtering paper is arranged below the special alpha nuclide filtering unit, and a rubber plug is additionally arranged on the inner side of the tank cover; sealant is poured into the seam of the special alpha nuclide filter unit and the air particle filter paper. The filtering efficiency of special alpha nuclide aerosol is larger than 99.99% through the gradient filtering design, the breathing resistance is reduced to 180 Pa or below by adopting high-specific-surface-area impregnated carbon (larger than 1000 m < 2 > / g), and the filtering efficiency and the performance stability of the filtering box are enhanced in the mode that the air particle filtering paper and the impregnated carbon are stacked.