88 results about "Gamma detection" patented technology

An infusion system may include a radioisotope generator that generates a radioactive eluate via elution, a beta detector, a gamma detector, and a controller. The beta detector and the gamma detector may be positioned to measure beta emissions and gamma emissions, respectively, emitted from the radioactive eluate. In some examples, the controller is configured to calibrate the infusion system using the gamma detector. For example, the controller may generate a radioactive eluate and measure the activity of the radioactive eluate using both the beta detector and the gamma detector. The high accuracy of the activity measured by the gamma detector may be used to calibrate the infusion system. In subsequent use, the infusion system calibrated using the gamma detector may adjust measurements made to monitor and / or control patient infusion procedures.

Apparatus, techniques and systems are described for facilitating identification of a target area during a probe-guided radio-localization surgical procedure. The described apparatus, techniques and systems can be used to implement a nuclear-uptake mode controller integrated into a probe to allow a user to instantly switch between multiple nuclear-uptake modes directly from the probe hand-piece. For example, a nuclear-uptake mode controller integrated into the probe can be used to instantly switch between a high-sensitivity nuclear uptake mode and a high-resolution nuclear-uptake mode toeffectively identify the target area in the presence of interfering nuclear signals by better matching the probe's nuclear detection parameters to a search task for that target area.

The invention relates to the technical field of gamma-ray spectrum analysis, particularly provides a gamma-ray detector activation analysis method and a PGNAA detection system, and aims to solve the problems that gamma rays obtained by detection of an existing gamma-ray detector comprise rays generated by decay of crystals after activation in a neutron field; therefore, the component detection result of the to-be-detected sample is not accurate. In order to achieve the purpose, the activation analysis method for the gamma detector comprises the steps that a to-be-detected sample is irradiated through a neutron source; repeatedly collecting a plurality of groups of gamma-ray energy spectrums of the sample to be detected by using a gamma-ray detector; constructing an energy spectrum signal matrix based on the gamma-ray energy spectrum of the to-be-detected sample, wherein the energy spectrum signal matrix is a mixed signal composed of instant gamma rays generated by neutron activation of the to-be-detected sample, environmental background gamma rays and interference signals generated by crystal activation in a gamma detector; and obtaining the effective instant gamma ray based on the energy spectrum signal matrix. The self-interference influence of the detector is effectively reduced, and the target element content evaluation precision of the to-be-detected object is improved.

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 embodiment of the invention relates to the field of neutron and gamma detection, in particular to a self-powered neutron and gamma integrated detector. The self-powered neutron-gamma integrated detector comprises a probe assembly and a control assembly, the probe assembly comprises a collector, a first insulating layer, a second insulating layer and emitters, the second insulating layer comprises a neutron insulating layer and a gamma insulating layer, and the emitters comprise a neutron emitter and a gamma emitter; the transmission cable is a three-core armored cable; the neutron insulating layer sleeves the outer side of the neutron emitter, and the gamma insulating layer sleeves the outer side of the gamma emitter; the neutron insulating layer is parallel to the gamma insulating layer; the first insulating layer is sleeved with the collecting body, and the bottom of the collecting body is filled with aluminum oxide powder; one end of the connecting device is connected with the receiving body, and the other end is connected with the cable housing. According to the embodiment, on-line measurement of the neutron signal and the gamma signal can be simultaneously carried out under the condition of high-temperature and high-pressure strong irradiation, and on-line monitoring of the neutron flux and the gamma flux of the reactor core can be simultaneously carried out.

The invention provides a positron annihilation lifetime-momentum correlation spectrometer for measuring a film sample, which comprises a detector module, an NIM electronics module, a data acquisition module and a data processing module, and is characterized in that the detector module comprises a gamma detector, a high-purity germanium detector and an anticoincidence module; the anticoincidence module, the high-purity germanium detector and the gamma detector are respectively connected with the NIM electronics module, and the NIM electronics module is sequentially connected with the data acquisition module and the data processing module. The positron annihilation life-momentum correlation measurement of the micron-sized film sample is realized, and the application of the technology in the field of material science is expanded.

The invention belongs to the field of nuclear radiation detection systems, and provides a portable neutron gamma detection system based on a NaIL crystal, the portable neutron gamma detection system 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 a buckle, and the handle is fixed on the support through a buckle. The detection device comprises a shell, a polyethylene moderator, a NaIL crystal, a photomultiplier, a front-end electronics part, a rear-end electronics part and a wireless communication antenna. The device is simple in structure and easy to hold and use or carry by a backpack, only one detection element is used, the structure of the detection device is greatly simplified, the front-end electronics part and the rear-end electronics part only need to consider processing of one path of signals, the equipment cost and the design difficulty are remarkably reduced, and the reliability is remarkably improved.

The invention belongs to the technical field of uranium exploration logging, and particularly relates to a small-caliber total gamma and gyro inclinometry combined logging probe tube, in the logging probe tube, a transmission outer sleeve and a probe tube pressure-bearing tube are fixedly connected with the two ends of a probe tube connector respectively, and the probe tube connector is fixedly connected to the transmission outer sleeve; a transmission circuit board framework is arranged in the transmission outer sleeve, an acquisition circuit board framework, a gyroscope framework, a gyroscope framework base and a gamma detector fixing copper column which are sequentially connected are arranged in the probe pressure-bearing pipe, and the gamma detector, the transmission circuit board framework and the acquisition circuit board framework are fixedly connected with the two ends of the probe connector respectively; the spring is positioned between the gamma detector and the probe tube bottom sealing head; the exploring tube bottom sealing head is fixedly connected with the exploring tube pressure-bearing tube; a gyroscope module is installed in the gyroscope framework, and a three-axis MEMS gyroscope is adopted as the gyroscope module. The total gamma measurement can be realized, and the azimuth angle and the inclination angle can be continuously measured in a ferromagnetic environment.

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.

The invention discloses a nuclear waste liquid gamma detection device which is communicated with a nuclear waste liquid discharge pipeline and comprises a measuring cylinder for containing nuclear waste liquid and an annular sodium iodide crystal detector fixedly assembled in the measuring cylinder. The maximum outer diameter of the annular sodium iodide crystal detector is smaller than the inner diameter of the measuring cylinder, and the distance between the bottom of the annular sodium iodide crystal detector and the bottom of the measuring cylinder is L; the annular sodium iodide crystal detector is provided with an annular sodium iodide crystal and an annular shell, the sodium iodide crystal is arranged in the shell, and the top of the shell is fixedly connected with a plurality of photomultiplication and signal processing assemblies coupled with the sodium iodide crystal. The nuclear waste liquid gamma detection device has the characteristics of low detection lower limit and high efficiency.

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 controllable dynamic scale device and method for a natural gamma detector. The controllable dynamic scale device comprises a system rack, a scale source box, a track system, a lifting mechanism, a control system and an acquisition system, the track system is fixed on the system rack, and the scale source box is arranged on the track system for sliding connection; lifting mechanisms are installed on the two sides of the scale source box and used for supporting a scale instrument. The control system is connected with the track system and a motor driving system of the lifting mechanism, and the acquisition system is connected with a calibrated instrument. By controlling the scale device to move on the track at a constant speed, the dynamic detection state of the logging instrument penetrating through the bottom layer underground is simulated, and accurate scale constants of the gamma probe at different speed measurement are obtained. The invention relates to a natural gamma scale theory, a scale system design scheme and a mechanical structure design and control method.

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 invention provides a gamma detector efficiency calibration method, device and equipment based on numerical integration, a medium and a program product. The method comprises the following steps: acquiring point source efficiency spatial distribution of a gamma detector; voxelizing the body source model of the to-be-detected body source to obtain a plurality of voxels; obtaining position efficiency corresponding to each voxel based on matching of the position information of each voxel and a point source position in point source efficiency space distribution; obtaining the distance from each voxel to the surface of the body source model in the ray direction pointing to the detection center of the gamma detector from each voxel, so as to obtain the attenuation length of each voxel; obtaining voxel efficiency of each voxel based on the attenuation length and the position efficiency of each voxel and the material attenuation coefficient of the to-be-measured body source; and processing the voxel efficiency of multiple voxels based on a passive efficiency calibration method of numerical integration to obtain the detection efficiency of the gamma detector on the to-be-detected body source.

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 present disclosure provides a gamma detection system, including a detection module for receiving incident gamma photons and obtaining the position information, energy information, and count information M of the gamma photons; a processing module for statistically analyzing the gamma photons within a certain period of time to obtain their projection distribution data p, determining the energy E of the incident photons according to the energy spectrum statistically obtained, and thereby reading in the pre-stored left and right singular matrices V, UT, and diagonal matrix S, and determining the number N of singular values to be retained according to the count information M; a reconstruction module for processing the diagonal matrix S according to the number N of singular values to be retained, calculating the generalized inverse matrix C+ of the transfer matrix C of the detection module according to C+ = VS+UT, and calculating the reconstructed image according to f = C+p; and a display module for displaying the reconstructed image f, the energy spectrum of the incident gamma photons, and the count information M. The present disclosure can quickly realize gamma radiation reconstruction imaging with a small amount of calculation and is convenient for integration with small hardware circuits.

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.

In one embodiment, contamination detection includes attaching a front-facing side of a detector enclosure to a ripper of a ripper machine. The detector enclosure includes a rear-facing side having a rear-facing window, two lateral-facing sides, and a bottom-facing side. A detector is disposed inside the detector enclosure. The ripper is inserted into a soil to position the rear-facing window, the two lateral-facing sides, and the bottom-facing side of the detector enclosure below a soil surface of the soil. The ripper is moved horizontally through the soil leading with the front-facing side of the detector enclosure to detect subsurface contamination via the rear-facing window using the detector.

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 preparation method of a gamma detector array based on a single crystal material, and relates to the technical field of gamma detection. The invention provides a preparation method of a perovskite single crystal material. The preparation method comprises the following steps: mixing methyl ammonium bromide powder and lead bromide powder, and dissolving in an N, N-dimethylformamide solvent to obtain an MAPbBr3 precursor solution; the preparation method comprises the following steps: dissolving formamidine chloride in an N, N-dimethylformamide solvent to obtain an FACl precursor solution; taking the FACl precursor solution, adding the MAPbBr3 precursor solution, mixing and clarifying to obtain an MAPbBr3-FACl solution; and filtering the MAPbBr3-FACl solution solvent, volatilizing and baking to obtain the perovskite single crystal material. The invention further provides a gamma ray detector array based on the perovskite single crystal material and a preparation method of the gamma ray detector array. The gamma ray detector array comprises the perovskite single crystal material, a low-power function metal layer and a high-power function metal layer, wherein the low-power function metal layer and the high-power function metal layer are deposited on the two faces of the perovskite single crystal material respectively.