42 results about "Gamma detection" patented technology

The invention discloses a hybrid neutron gamma detector array and a signal processing method, and relates to the technical field of nuclear physical detection.During detection, eight EJ200 scintillators arranged in an array are used for energy deposition of gamma rays and fast neutrons and generating photons, and meanwhile three EJ426 thermal neutron scintillation screens are used for capturing thermal neutrons and generating photons; the response of gamma rays, fast neutrons and thermal neutrons is realized at the same time, and the detection precision is greatly improved. Meanwhile, if the three EJ426 thermal neutron scintillation screens are alternately stacked front and back, the total reflection of the EJ200 scintillators and the semi-light-proof performance of the EJ426 thermal neutron scintillation screens are utilized to block photon propagation in the X direction and only enable photons to be propagated in the Y direction and the Z direction, and each EJ200 scintillator corresponds to a four-channel photon collection structure to perform high-efficiency collection of the photons, so that the high-efficiency collection of the photons is realized. Therefore, high-precision detection and high-efficiency photon collection are realized, and support is provided for subsequent intense radiation field monitoring or high-precision positioning.

The invention discloses a control method and device of a material moisture online monitoring system and a storage medium, and relates to the technical field of material moisture monitoring, and the method comprises the steps: starting a neutron generator assembly, and starting a neutron detector assembly and a gamma detector when the starting duration of the neutron generator assembly is greater than or equal to the preheating preset duration; based on a detection result of the neutron detector assembly, determining an accumulated scattering neutron share of the detected material, and obtaining a corresponding target hydrogen density matched with the accumulated scattering neutron share from a preset association library; based on a gamma detector, counting the monitored gamma rays in a classified manner according to the pulse amplitude, generating a gamma-ray energy spectrum, and extracting a water hydrogen characteristic peak area from the gamma-ray energy spectrum; according to the target hydrogen density, the water-hydrogen characteristic peak area and the energy spectrum calibration coefficient of the gamma-ray energy spectrum, the curing hydrogen ratio is determined; and determining the free water content of the detected material according to the cured hydrogen ratio. According to the invention, through dual-mode cooperative detection, the problem of low accuracy of moisture monitoring is solved.

The utility model discloses a storage type gamma magnetic positioning combined logging instrument which comprises a shell, a thermos bottle and a CCL magnetic detection assembly are fixedly arranged in the shell, and a gamma detection assembly and a circuit module are arranged in the thermos bottle and used for collecting, processing and storing gamma data and CCL signal data. The gamma detection assembly is arranged below the circuit module; the gamma detection assembly and the CCL magnetic detection assembly are electrically connected with the circuit module. The two ends of the shell are provided with a protective cap and a protective plug in a threaded connection mode respectively. According to the storage type gamma magnetic positioning combination logging instrument, the two logging units of the gamma energy spectrum instrument and the CCL instrument are designed and combined into one logging unit, the length of the instrument is shortened, the logging construction risk is greatly reduced, the pumping-out or direct pushing technology is adopted, real-time data storage is achieved in the logging process, and the logging efficiency is improved. The defects existing in cable type logging are well overcome.

This invention relates to a portable on-site detection device and method for Lu-177 radionuclide activity. The detection device includes a gamma detection assembly and a circuit board installed within a housing. The gamma detection assembly comprises several pieces, each housing a gamma detection module. The space formed by the gamma detection assemblies serves as a sample chamber, with a central slot for holding a Lu-177 carrier bottle. The gamma detection module employs a combination structure of a GAGG:Ce scintillator and a silicon photomultiplier tube (SiPM). The circuit board houses a connection module between the circuit board and the gamma detection assembly, a power conversion module, a signal summing circuit for the gamma detection assembly, a digital multichannel module, and a data analysis and transmission module. The testing method includes five steps, including device initialization. The beneficial effects are that it provides technical support for accurate pre-administration dose verification of Lu-177, ensuring medication safety for patients undergoing radionuclide therapy and improving the quality of clinical nuclear medicine treatment.

This application discloses a control method, device, and storage medium for an online material moisture monitoring system, relating to the field of material moisture monitoring technology. The method includes: starting a neutron generator assembly; when the start-up time of the neutron generator assembly is greater than or equal to a preset preheating time, activating a neutron detector assembly and a gamma detector; determining the cumulative scattered neutron share of the measured material based on the detection results of the neutron detector assembly, and obtaining the cumulative scattered neutron share to match the corresponding target hydrogen density from a preset correlation library; generating a gamma spectrum based on the gamma rays monitored by the gamma detector according to pulse amplitude classification and counting, and extracting the water hydrogen characteristic peak area from the gamma spectrum; determining the solidified hydrogen ratio based on the target hydrogen density, the water hydrogen characteristic peak area, and the energy spectrum calibration coefficient of the gamma spectrum; and determining the free water content of the measured material based on the solidified hydrogen ratio. This application solves the problem of low accuracy in moisture monitoring through dual-modal collaborative detection.

This invention discloses a neutron analysis physics testing system and method, belonging to the field of nuclear physics testing technology. The system includes: a high-speed synchronous pulse generator for generating pulse signals with multiple modulation sequences; an ultrashort pulse neutron generator for emitting short pulse neutron rays with specified parameters onto a sample; a neutron detector for acquiring secondary neutron signals; a gamma detector for acquiring characteristic gamma signals generated by neutron-excited probes of the sample; a safety control module for controlling the operating state of the ultrashort pulse neutron generator; and a data processing device for real-time collection and summarization of neutron signals and characteristic gamma signals based on the timing of the pulse signals with multiple modulation sequences. This system reduces time window drift and measurement errors, and activates the ultrashort pulse neutron generator only when a gate signal allows, improving the accuracy, safety, and stability of geological physics parameter measurements.

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 petroleum and natural gas drilling, and discloses a portable integrated gamma detector detection device and method. An AC-DC module and a pulse counting acquisition communication board are arranged in a shell; wherein an LCD (liquid crystal display) screen, a multichannel digital current display nixie tube group, a multichannel USB (universal serial bus) power supply and pulse acquisition interface group, a power supply switch and a USB communication interface are respectively arranged on the surface of the front panel, a power switch interface is arranged on the rear panel, and the power switch interface is converted into + 24VDC and + 5VDC power supplies through an internal AC-DC (alternating current-direct current) module. Wherein the + 24VDC is output to the four-channel USB power supply and data acquisition interface for supplying power to the integrated gamma detector, and the + 5VDC is used for supplying power to the pulse counting acquisition communication board, the LCD display screen and the four-channel digital current display nixie tube; the LCD display screen is used for displaying the gamma counting rate of the four channels in real time; four-channel current and counting rate visual display is provided, the operation complexity is reduced, the detection efficiency is improved, and the in-factory detection and maintenance efficiency of the detector is greatly improved.

The invention discloses a uranium mine logging instrument based on ultrashort pulse neutrons and a working method thereof, and relates to the field of uranium mine exploration logging. The logging instrument comprises a control communication short section, an ultrashort pulse neutron generator used for emitting fast neutron pulses with the pulse width smaller than 1 microsecond to a stratum, a shielding body and a double-thermal-neutron detection assembly used for detecting thermal neutrons and epithermal neutrons on measuring points consistent in space, all of which are sequentially arranged in the axial direction of the logging instrument. The gamma detector is used for detecting inelastic scattering gamma rays emitted by stratum elements and capturing gamma rays, and the fast neutron detector is used for detecting and outputting source intensity monitoring signals of fast neutron pulses in real time. According to the logging instrument, the ultra-short fast neutron pulse is emitted, the neutron yield is detected in real time, the neutron time spectrum and gamma-ray energy spectrum multi-dimensional information with an accurate timestamp are obtained in a combined mode, high-precision and anti-interference inversion is conducted on the stratum uranium content, and stratum information is obtained efficiently and accurately.

The application discloses a positron annihilation lifetime measurement device and method for thin film sample characterization, which is composed of a positron emitter, a positron detector and a gamma detector; a sample is placed between the positron emitter and the positron detector. The positron emitter contains a radioactive source and is responsible for detecting the positrons entering the sample, and the positron detector is responsible for detecting the positrons penetrating the sample. The gamma detector is responsible for detecting the 0.511 MeV gamma photons generated after the positrons are annihilated. The application can break through the limitation of measuring the sample thickness, is suitable for all types of positron radioactive sources, and sufficiently widens the experimental conditions; meanwhile, the non-contact measurement function can expand the application of the positron annihilation lifetime measurement method in the measurement of special samples and special environments.

The invention discloses a neutron analysis physical testing system and method, and belongs to the technical field of nuclear physical testing. The system comprises a high-speed synchronous pulse generator used for generating pulse signals of various modulation sequences; the ultrashort pulse neutron generator is used for emitting short pulse neutron rays with specified parameters to the sample; the neutron detector is used for acquiring a secondary neutron signal; the gamma detector is used for acquiring a characteristic gamma signal generated by the neutron excitation detection sample; the safety control module is used for controlling the working state of the ultrashort pulse neutron generator; and the data processing device is used for collecting and gathering neutron signals and characteristic gamma signals in real time according to the time sequence of the pulse signals of the multiple modulation sequences. According to the system, time window drift and measurement errors are reduced, the ultra-short pulse neutron generator is started only under the condition that access control signals allow, and the accuracy, safety and stability of stratum physical parameter measurement are improved.

A method, system, apparatus, and computer-readable program product for determining the count rate linearity of one or more gamma detectors using a single gamma radiation source by varying the solid angle between the single gamma radiation source and one or more detectors (and therefore the emissivity observed by the detectors).

The application provides a source device-based positron annihilation lifetime measurement system and method, which comprises a source chamber, a start gamma detector, a stop gamma detector and a positron detector. 22 The Na radioactive source is fixed on the surface of the source chamber, the source chamber and the positron detector are placed on the two sides of the thin film sample and are symmetrically opposite, and the positions are relatively fixed; the start gamma detector and the stop gamma detector are placed on the two sides of the positron detector and are responsible for detecting the 1.28 MeV gamma photons generated by the cascade when the positron is emitted by the radioactive source and the 0.511 MeV gamma photons generated after the positron annihilation. The application can effectively remove the noise positrons by improving the positron range on the non-sample side, reducing the detection efficiency of the far-end annihilation gamma photons, and reducing the size of the electronics; the positron annihilation position on the sample side can be accurately identified, the non-sample positron annihilation components can be excluded, the sample thickness limitation can be broken, and the thin film sample positron annihilation lifetime measurement can be realized.

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 application discloses a mixed neutron gamma detector array and a signal processing method, and relates to the technical field of nuclear physics detection.The eight EJ200 scintillators arranged in the array are used for energy deposition of gamma rays and fast neutrons and for generating photons, and three EJ426 thermal neutron scintillation screens are used for capturing thermal neutrons and generating photons, so that the responses of the gamma rays, the fast neutrons and the thermal neutrons are realized at the same time, and the detection precision is greatly improved.Meanwhile, when the three EJ426 thermal neutron scintillation screens are alternately stacked in front and back, the total reflectivity of the EJ200 scintillators and the semi-opaque property of the EJ426 thermal neutron scintillation screens are utilized to block the propagation of the X-direction photons, so that the photons only propagate in the Y and Z directions, and the four-channel photon collection structure corresponding to each EJ200 scintillator is utilized to collect the photons with high efficiency, so that high-precision detection and high-efficiency photon collection are realized, and support is provided for subsequent strong radiation field monitoring or high-precision positioning.

The utility model discloses a double-spacing integrated gamma detector and a logging instrument, and relates to the field of uranium exploration logging. The detector comprises a shell, a double-probe assembly and a readout electronics module, wherein the double-probe assembly is composed of a near-spacing probe and a far-spacing probe; the near source distance probe and the far source distance probe are fixedly arranged in the shell at an interval and are both arranged to be radiation-resistant scintillation crystals connected with photoelectric converters; a central cavity is defined between the near source spacing probe and the far source spacing probe as well as the inner wall surface of the shell, and the readout electronics module is integrally arranged in the central cavity; the inner wall surface of the shell is coated with a shielding layer; according to the detector, the spatial multiplexing architecture is combined with mechanical rigid fixation, so that the structure is compact, the source distance offset is eliminated, and the measurement reliability is improved.

The invention discloses an activation source three-dimensional radioactive intensity inversion method and system based on gamma detector counting and a storage medium, and belongs to the field of radiation field calculation in the nuclear facility decommissioning process. The method comprises the following steps: measuring and acquiring a characteristic gamma-ray energy spectrum of an activation source through a detector by adopting an experimental measurement mode; performing appropriate grid division on the geometric model of the activation source; measuring the photon flux generated by the activation source at different positions in the space, and obtaining the coordinate of the measuring point position and the photon count of the detector; based on a Monte Carlo method, constructing a response model of the detector to the activation source, and obtaining a three-dimensional space response function of the detector through Monte Carlo forward calculation; based on the three-dimensional space response function, a response equation set between detector counting and activation source grid activity is established, and three-dimensional activity distribution of the activation source is obtained through inversion by solving the equation set. According to the invention, reverse inversion of three-dimensional activity distribution of the activation source based on counting of the gamma detector can be realized, and detailed neutron irradiation information does not need to be acquired.

The invention discloses a packaged gamma detector based on underground drilling, and relates to the technical field of gamma detectors, and the packaged gamma detector comprises a shell which is internally provided with a containing cavity; the scintillator is arranged in the accommodating cavity and is used for detecting gamma rays; and the photomultiplier is fixedly connected to one side, far away from the scintillator, in the accommodating cavity and is used for receiving the optical signal. Through the arranged buffer assembly, when the detector is subjected to axial impact, the shell and the photomultiplier generate axial displacement, the vibration ring triggers the air buffer piece due to relative lag of inertia, impact energy is absorbed through air viscous damping, and under axial or radial impact, the movement of the slip ring drives all the radial abutting blocks to synchronously and radially move, so that the vibration of the detector is reduced, and the reliability of the detector is improved. The inner wall of the shell is actively abutted against or loosened, dynamic deviation correction of the supporting sleeve and the scintillator is achieved, light path alignment is ensured, the drilling precision is improved, and the quality of a borehole drilled for underwater oil and gas production equipment is directly improved.

An instrument and software methodology to detect a radioactive source and incorporates the following:1) two radiation detectors in a co-axial configuration, housed in a handheld probe, and2) a gamma detection control unit executing software algorithms to limit the functional field of view to the front aspect of the probe, vary the depth and width of the field of view to provide collimation without the use of metallic shielding, and allowing the instrument to measure the distance to the radiation source. Due to the shielding effect that the forward detector has on the rear detector, several mathematical factors must be applied to the basic equations utilized for a front / rear detector system, as is disclosed herein.

The application discloses a packaged gamma detector based on downhole drilling, and relates to the technical field of gamma detectors, which comprises a shell, an accommodating cavity is formed in the shell, a scintillator is arranged in the accommodating cavity and used for detecting gamma rays, and a photomultiplier is fixedly connected to one side of the accommodating cavity away from the scintillator and used for receiving optical signals. When the detector is subjected to axial impact, the shell and the photomultiplier generate axial displacement, the vibration ring triggers the air buffer due to inertia, the impact energy is absorbed through air viscous damping, under axial or radial impact, the movement of the slip ring drives synchronous radial movement of all radial resistance blocks, the shell inner wall is actively pressed or loosened, dynamic deviation correction of the supporting sleeve and the scintillator is realized, the optical path is aligned, drilling precision is improved, and the quality of drilling a well hole for underwater oil and gas extraction equipment is directly improved.

The invention belongs to the technical field of nuclear radiation measurement and radiation protection, and relates to a shielding device for a gamma detector, the shielding device comprises a shielding box body, a shielding assembly and a controller, a through ray channel is arranged in the shielding box body, the ray channel comprises an inlet end and an outlet end, the outlet end is used for installing a gamma detector probe, and the controller is connected with the shielding assembly. The shielding assembly comprises a shielding body and a driving unit. The output end of the driving unit is connected with the shielding body. The shielding body comprises a plurality of shielding sections arranged in the direction perpendicular to the connecting line of the inlet end and the outlet end, the shielding capacity of the shielding sections is sequentially reduced, and each shielding section is used for blocking the inlet end. According to the scheme, the position of the shielding body can be automatically adjusted, the counting rate is made to be within the preset counting rate interval, and the method and device are suitable for scenes where gamma ray fluctuation in the environment is large and gamma rays of the to-be-detected sample change.

A method and system for determining a density. The method may comprise disposing a nuclear density tool into a wellbore, performing a spectral deconvolution, determining an energy channel for a first measurement layer, recording a count rate with the gamma detector for the first measurement layer, applying a slope operator to the count rate, and identifying a first density of the first measurement layer. The system may comprise a nuclear density tool that includes a gamma source and a gamma detector configured to record a count rate, wherein the gamma detector and the gamma source are disposed on a longitudinal axis of the nuclear density tool. The system may also comprise an information handling system.

The application discloses a kind of uranium mine logging instrument based on ultrashort pulse neutron and working method thereof, it is related to uranium mine exploration well logging field;Logging instrument includes control communication nipple arranged in sequence along its axial direction, ultrashort pulse neutron generator for emitting fast neutron pulse with pulse width less than 1 microsecond to formation, shielding body, dual thermal neutron detection assembly for detecting thermal neutron and superhot neutron on spatially consistent measurement point, gamma detector for detecting non-elastic scattering gamma ray and capture gamma ray emitted by formation element, and fast neutron detector and multichannel synchronization and high-speed acquisition circuit for detecting and outputting source intensity monitoring signal of fast neutron pulse in real time;The logging instrument of the application emits ultrashort fast neutron pulse and detects neutron yield in real time, combines to obtain neutron time spectrum and multi-dimensional information of gamma energy spectrum with accurate time stamp, carries out high-precision, anti-interference inversion to formation uranium content, and efficiently and accurately obtains formation information.

This application discloses a calibration method, device, and storage medium for material composition analysis, relating to the field of automated analysis technology. The method includes: matching a first gamma spectrum obtained from the detection data of a first gamma detector with material parameters from a parameter library; calculating an equivalent mass thickness based on the characteristic peak area of ​​a second gamma spectrum obtained from the acquisition data of a second gamma detector, the material parameters, and the initial gamma-ray characteristic peak area of ​​a radioactive source; generating a correction factor through scaling transformation based on the equivalent mass thickness and the material parameters; and correcting the initial material composition matched in the parameter library using the correction factor to obtain material composition data. This method solves the problem of excessive deviation in material composition monitoring data and reduces the error in cement composition analysis under complex working conditions.

A logging or measuring while drilling tool includes a semi-tubular housing base having first and second portions. A first semi-tubular lid is releasably connected to the first portion. The first semi-tubular lid and first portion of the semi-tubular housing base provides a first enclosure for containing a sensor. The sensor may be cylindrically shaped with an outer cylindrical surface that extends laterally between the first and second flat end surfaces. The outer cylindrical surface of the sensor may engage the first semi-tubular lid.

The utility model relates to the technical field of gamma detection equipment, in particular to a natural gamma measurement probe tube for an inclinometer while drilling, which comprises a gamma measurement probe tube mechanism, a gamma measurement probe tube mechanism and a gamma measurement probe tube mechanism, the sliding mechanism comprises a half pipe frame I and a half pipe frame II, and the sliding mechanism is screwed in the outer pipe and can slide along with the outer pipe, so that maintenance and inspection of parts are facilitated; and the multiple limiting frame mechanisms are inserted into the sliding mechanisms, and local parts can be independently disassembled. According to the utility model, the half-pipe frame I and the half-pipe frame II can be spliced, and a plurality of limiting frame mechanisms are inserted between the half-pipe frame I and the half-pipe frame II, so that fault parts can be accurately positioned and independently replaced, the maintenance efficiency is greatly improved, the maintenance time and cost are reduced, and drilling operation stagnation caused by equipment faults is reduced; and internal parts do not need to be disassembled one by one.

The application belongs to the field of nuclear radiation detection system, and provides a portable neutron gamma detection system based on NaIL crystal, which comprises a detection device, a tablet computer, a support, and a handle, the support and the handle are installed on the detection device through a plurality of groups of fastening bolts and spring washers, the tablet computer is fixed on the support through buckles, and the detection device comprises a shell, a polyethylene moderator, a NaIL crystal, a photomultiplier tube, a front-end electronic part, a rear-end electronic part, and a wireless communication antenna. The application has simple structure, is easy to hold and use or carry in a backpack, only uses one detection element, greatly simplifies the structure of the detection device, only needs to consider the processing of one-way signal for the front-end electronic part and the rear-end electronic part, significantly reduces the equipment cost and design difficulty, and significantly improves the reliability.

A logging or measuring while drilling tool includes a semi-tubular housing base having first and second portions. A first semi-tubular lid is releasably connected to the first portion. The first semi-tubular lid and first portion of the semi-tubular housing base provides a first enclosure for containing a sensor. The sensor may be cylindrically shaped with an outer cylindrical surface that extends laterally between the first and second flat end surfaces. The outer cylindrical surface of the sensor may engage the first semi-tubular lid.

The invention discloses a gamma counter energy spectrum generation method based on digital waveform analysis. The method comprises the following steps: 1) screening out a plurality of candidate peaks from analog pulse signals output by a gamma detector for detecting a target gamma source; 2) for each candidate peak, calculating an average change slope Kavg and an amplitude variation delta V of the candidate peak; 3) respectively comparing the average change slope Kavg and the amplitude variation delta V of the candidate peak with a slope threshold value Kth and an amplitude difference threshold value delta Vth, if Kavg is greater than or equal to Kth and delta V is greater than or equal to delta Vth, judging that the candidate peak is an effective gamma signal peak and transmitting the effective gamma signal peak to a subsequent data processing module, otherwise, judging that the candidate peak is a noise false peak; and 4) the data processing module generates the gamma-ray energy spectrum of the target gamma-ray source according to the received gamma-ray signal peak. According to the invention, the synchronous optimization of the energy spectrum resolution and the measurement sensitivity can be realized, the anti-interference capability is strong, and the robustness is high.

The invention relates to a portable Lu-177 nuclide activity field detection device and a test method. The detection device comprises a gamma detection assembly and a circuit mainboard which are installed in a shell. A plurality of gamma detection assemblies are arranged, the gamma detection modules are mounted in the gamma detection assemblies, a space formed by surrounding the gamma detection assemblies is used as a sample cabin, a clamping groove in the center of the sample cabin is used for placing a Lu-177 bearing bottle, and each gamma detection module adopts a GAGG: Ce scintillator and silicon photomultiplier SiPM combined structure; the circuit mainboard is provided with a connection module of the circuit mainboard and the gamma detection assembly, a power conversion module, a signal summation circuit of the gamma detection assembly, a digital multi-channel module and a data analysis and transmission module. The test method comprises five steps of device initialization and the like. The method has the beneficial effects that a technical support is provided for accurate checking of the dosage before Lu-177 administration, the medication safety of a nuclide treatment patient is guaranteed, and the clinical nuclear medicine treatment quality is improved.