48 results about "Gamma photon" patented technology

A positron emission tomography (PET) scanner may include a plurality of gamma radiation detector modules arranged to form a detector ring. Each detector module may include an array of elongated scintillation crystals. With respect to the detector ring, each elongated scintillation crystal includes a proximal end-face, two axially oriented lateral faces, two transaxially oriented lateral faces, and a distal end-face radially oriented into the detector ring to receive a gamma photon. An array of photosensors is positioned along a first of the axially oriented lateral faces of each elongated scintillation crystal to detect scintillation photons. A reflective material is positioned on the proximal end-face, the distal end-face, the transaxially oriented lateral faces, and a second of the axially oriented lateral faces of each elongated scintillation crystal to internally reflect scintillation photons. In various embodiments, a dual-channel processing circuit provides distinct timing and energy signals from the photosensors.

A positron emission tomography (PET) scanner includes multiple gamma radiation detector modules arranged to form a detector ring. Each detector module includes an array of elongated scintillation crystals. With respect to the detector ring, each elongated scintillation crystal includes a proximal end face, two axially-oriented side faces, two cross-axially-oriented side faces, and a distal end face oriented radially into the detector ring to receive gamma photons. An array of photosensors is disposed along a first of the axially-oriented side faces of each elongated scintillation crystal to detect scintillation photons. Reflective material is disposed on a second of the proximal end face, the distal end face, the cross-axially-oriented side face, and the axially-oriented side face of each elongated scintillation crystal to internally reflect scintillation photons. In various embodiments, a dual-channel processing circuit provides separate timing and energy signals from the photosensors.

This invention provides a cascaded imaging diagnostic and therapeutic integrated system, relating to the field of imaging. The system includes: a gantry, a slit collimator, a detector ring, and a base. The gantry is a hollow, regular prism. The slit collimator is mounted on the inner side wall of the gantry; the detector ring is mounted on the outer side wall of the gantry; the side wall of the gantry is mounted on the base. When a living organism to be detected is transferred into the cavity of the gantry, the detector ring images the target position within the organism through the slit collimator. The living organism carries a drug containing a nuclide that supports the emission of cascaded photons. The detector ring is connected to a host computer. This invention can collimate and detect "cascaded gamma photon pairs," thereby directly locating the nuclide decay position, achieving real-time imaging, short imaging time, and avoiding the defects of traditional nuclear medicine image reconstruction.

The invention discloses a high-efficiency multichannel positron annihilation lifetime measurement method and device. The method comprises the following steps: 1) detecting instant gamma photons generated by positron of a target radioactive source and positron annihilation gamma photons by using a plurality of detectors, converting the instant gamma photons and the positron annihilation gamma photons into analog signals, and sending the analog signals to a sampling circuit; 2) a sampling circuit is responsible for sampling and digitally processing analog signals generated by each detector and then uploading the analog signals to an upper computer; and 3) the upper computer analyzes and processes the uploaded data to obtain the positron annihilation lifetime of the target radioactive source. The sampling circuit comprises a trigger module, a sampling module, a digital module and a control module. The control module configures each module according to a program issued by upper computer program control software. When the detector input signal meets the setting of the trigger module, the sampling module starts or stops sampling the detector signal of each channel; the digital module carries out digital processing on the signals, converts the signals into data and uploads the data to an upper computer.

The invention relates to the technical field of nuclear, in particular to a device for detecting selenium content in fruits, which comprises a D-D neutron generator and a measuring chamber, the D-D neutron generator generates neutrons, the neutrons in the measuring chamber enter a sample to generate nuclear reaction with atomic nucleuses in the sample in the measuring chamber, and the neutrons in the measuring chamber are generated; after the atomic nucleus of the measuring chamber is activated, instant gamma rays and delayed gamma rays are released; the high-purity germanium detector in the measuring chamber receives delayed gamma rays of all elements in the sample in the measuring chamber and converts each gamma photon into an electric pulse signal; the multichannel analyzer is used for converting the electric pulse signals of the measuring chamber into digital signals, dividing channel addresses according to the size of the digital signals, counting the pulse number and forming a gamma ray energy spectrum; and the computer in the measuring chamber calculates the selenium content in the sample in the measuring chamber through the gamma ray energy spectrum in the measuring chamber. The method has the advantages of low detection limit, small error and high measurement result precision, and can quickly realize the detection of the selenium content in the fruits.

A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

Methods and apparatus for using exempt gamma photon sources to measure fluid properties are described herein. The gamma photon sources are used with detectors in an arrangement that provides a short photon path length between source and detector. Fluid measurement devices described herein have a fluid container defining an interior, an exempt gamma-ray source located outside the fluid container, and a gamma-ray detector located outside the fluid container, the exempt gamma photon source and the gamma-ray detector defining a photon path that traverses the interior of the fluid container along a non-diametric chord of the fluid container.

Reconstruction of simultaneous occurrence data of immediate gamma in PET scanning is provided. The invention discloses a method for identifying instant gamma rays through three-photon detection. The method involves using two annihilation photons and one immediate gamma photon to determine the direction of the corresponding immediate gamma ray.

A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

This disclosure provides a gamma camera with a collimation unit, applicable to the field of detection technology. The gamma camera includes at least one detection unit, comprising: a collimation unit comprising multiple needle-type collimator arrays arranged alternately, each needle-type collimator array comprising multiple arrayed needle-type collimators whose length directions point in the same direction, with the length directions of the needle-type collimators in different arrays pointing in different directions; multiple scintillation crystal units for detecting gamma photons penetrating the collimation unit along different directions, generating multiple sets of scintillation light signals; and multiple photoelectric conversion units, each coupled to a scintillation crystal unit, for converting the multiple sets of scintillation light signals into multiple sets of electrical signals for imaging by the gamma camera.

The application relates to an emission type computer tomography detector. The detector comprises a plurality of semiconductor wafers, a crystal array and a circuit board. Each semiconductor wafer is a silicon photomultiplier chip body, the crystal array comprises a plurality of regularly arranged crystals, one or more semiconductor wafers are arranged on each crystal, and the semiconductor wafer and the corresponding crystal are integrally packaged; the circuit board is arranged on one side of the crystal array, and each semiconductor wafer is electrically connected with the circuit board. The semiconductor wafer is integrally packaged with the crystal, i.e. the glass cover plate and the substrate can be cancelled, when the crystal receives gamma photons, the fluorescence emitted by the crystal can directly enter the semiconductor wafer without passing through the glass cover plate, thereby avoiding the loss of the fluorescence when the fluorescence passes through the glass cover plate and the silicon oil, so that the performance of the detector is improved.

The application discloses a method for imaging airtight inner cavity of an aero-engine by using a low-cost positron emission tomography device with good imaging quality, and the gamma photon detection mechanism of the positron emission tomography device comprises an embedded rotary flat plate detection device and a ring-shaped detection device; the ring-shaped detection device comprises a cylindrical mounting frame, and the inner wall of the cylindrical mounting frame is covered with second gamma photon detection crystals; the embedded rotary flat plate detection device comprises a mounting flat plate and a driving device for driving the mounting flat plate to rotate around the central axis of the ring-shaped detection device, and the mounting flat plate is provided with a plurality of first gamma photon detection crystals; the central angle of the cylindrical mounting frame corresponding to the first gamma photon detection crystals of the first detection crystal array is 60-90 degrees; and the diameter of the second detection crystal array is 1.6-2.6 times the distance between the first detection crystal array and the central axis of the ring-shaped detection device.

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.

A novel method is disclosed for obtaining transmission scan data in a PET scanner by incorporating one or more stationary gamma ray sources that provide forward scattered gamma photons that can be used as transmission imaging radiation.

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 relates to a gamma photon positioning method and device for an orthogonal strip-shaped tellurium-zinc-cadmium detector. The method comprises the following steps: acquiring current signals respectively generated by interaction of a plurality of gamma rays and the orthogonal strip-shaped tellurium-zinc-cadmium detector; vectorizing the plurality of current signals to obtain an input vector set; an initialized neural network is constructed based on the positions of a plurality of electrode strips in the orthogonal strip-shaped cadmium zinc telluride detector, and the number of initialized neurons is the same as that of the plurality of electrode strips; performing weight vectorization processing on the plurality of initialized neurons to construct an initialized weight vector set; and based on the input vector set and the initialized weight vector set, iteratively reducing the range of the initialized weight vector set through a self-organizing mapping algorithm to obtain a target weight vector, and determining the position of the gamma photon. The purpose of determining the position of the gamma photon based on the neural network and the self-organizing mapping algorithm is achieved, and therefore the technical effects of improving the accuracy of the position of the gamma photon and improving the position obtaining efficiency are achieved.

The embodiments of the present disclosure provide an imaging system, the imaging system may include a volume coil; a support assembly, wherein the volume coil is configured to surround an outer side of the support assembly or the support assembly is configured to surround an outer side of the volume coil; and a detector, installed on the support assembly and configured to receive gamma photons generated by radionuclides from a subject.

The application provides a scattering correction method and device, a digital device and a computer readable storage medium. The method comprises the following steps: obtaining a corresponding relationship function of one-dimensional detection energy spectrum and one-dimensional gamma photon energy spectrum; based on the corresponding relationship function, using a maximum likelihood-expectation maximization iterative algorithm to obtain two one-dimensional gamma photon energy spectrums corresponding to each down-sampling response line; based on the one-dimensional gamma photon energy spectrums, obtaining the number of non-scattering single events corresponding to each down-sampling response line; based on the total number of single events and the number of non-scattering single events corresponding to each down-sampling response line, calculating the number of scattering coincidence events corresponding to each down-sampling response line; performing up-sampling processing on the down-sampling response line to obtain an up-sampling response line; and calculating the number of scattering coincidence events corresponding to each up-sampling response line. When the scattering correction is performed, the application has the advantages of simple implementation and high accuracy.

The present disclosure relates to a two-dimensional positron annihilation lifetime spectrum measurement method and system, which relates to the fields of nuclear spectroscopy and nuclear detection technology. This method detects the first stop time and the second stop time of the two annihilation gamma photons generated in the reverse direction when the positron annihilates, respectively. The first lifetime value and the second lifetime value are then calculated from the start time of the initial gamma photon generated by the decay of the radioactive source, respectively. The first lifetime value and the second lifetime value are then subjected to two-dimensional statistics to obtain a two-dimensional positron annihilation lifetime spectrum of the positron annihilation in the sample to be tested. This method performs statistics on the two annihilation gamma photons generated by an annihilation case, which can effectively eliminate background counts, thereby improving the peak-to-valley ratio of the lifetime spectrum, and can improve the utilization rate of the annihilation gamma photon information in the annihilation case, thereby improving the time resolution of the measurement.

The invention relates to medical imaging equipment, a collimator and a processing method of the collimator. As the two adjacent rows of collimation holes of the collimation body are arranged in a staggered manner, if a cross splicing method in the prior art is adopted, splicing seams are formed in the collimation holes, so that parts of the collimation holes are shielded by the splicing seams, or the splicing seams are formed between the two collimation holes, so that the thickness of a partition plate between the two collimation holes is increased; therefore, part of gamma photons capable of entering the collimation hole are blocked, the sensitivity of the part is reduced, and the uniformity of the collimator is influenced. According to the invention, the splicing edge of the collimator is designed, so that in the collimator formed by splicing, the splicing seam is located in the collimation hole, although the splicing seam is formed in the collimation hole, the equivalent aperture of the collimation hole at the splicing seam is not changed, namely the effective aperture is not changed, so that the counting of gamma photons entering the collimation holes is consistent, and the accuracy of the gamma photons entering the collimation holes is improved. Therefore, the uniformity of the collimator can be ensured, and the image quality is further ensured.

This invention provides a technetium-99m preparation system, its usage method, and its applications. The system includes a reaction module and a purification module. The reaction module includes an electron beam channel, a shell, and a gamma photon fabrication unit inside the shell, forming a Mo-containing solution region between the shell and the gamma photon fabrication unit. The gamma photon fabrication unit is used to produce gamma photons, and the Mo-containing solution region is used to contain the Mo-containing solution and carry out the reaction. The gamma photon fabrication unit includes a metal outer layer and at least one target plate disposed inside the metal outer layer. The electron beam channel penetrates the shell and connects to the metal outer layer of the gamma photon fabrication unit. The Mo-containing solution region and the purification module also include a circulation loop. The mixture generated in the Mo-containing solution region is passed through the circulation loop into the purification module for purification to form a technetium-99m separation solution and a Mo separation solution. The Mo separation solution is returned to the Mo-containing solution region through the circulation loop. By using the technetium-99m preparation system provided by this invention, low-cost and high-efficiency production of technetium-99m can be achieved.

The application belongs to the technical field of medical treatment and provides a prompt gamma photon event identification method, a data reconstruction method and an electronic device. The prompt gamma photon event identification method comprises the following steps: obtaining first TOF data of a double-coincidence event detected by a detector, the double-coincidence event being two simultaneous associated events; determining second TOF data of a triple-coincidence event according to the first TOF data, the triple-coincidence event being three simultaneous associated events; performing one or more verification operations to determine a prompt gamma photon position; and determining a prompt gamma photon event in the triple-coincidence event based on the prompt gamma photon position. The embodiments of the application can effectively identify the prompt gamma photon event by using the TOF data, which is helpful to separate the double-nuclide signal.

The invention discloses nuclide imaging equipment with adjustable detector spacing, which comprises an image bin, a detection mechanism is arranged in the image bin, the detection mechanism comprises a disc mounted in the image bin, a round hole is formed in the middle of the disc, and a plurality of nuclide imaging detectors are mounted on the disc. The front ends of the nuclide imaging detectors are tightly attached to form a first regular polygon, the disc is further provided with a distance adjusting mechanism, and the distance adjusting mechanism is used for driving a plurality of nuclide imaging detectors to move towards the end close to the round hole, so that the front ends of the nuclide imaging detectors are tightly attached to form a second regular polygon. According to the invention, the positions of the nuclide imaging detectors are moved through the spacing adjusting mechanism, so that the front ends of the plurality of nuclide imaging detectors are tightly attached to form regular polygons with different sizes, and the regular polygons are respectively adaptive to detection objects with different body types, so that the nuclide imaging detectors can fully receive gamma photons emitted by a living body; and the imaging effect is good.

A neutron flux detector comprising a source material and a solid state radiation detector is disclosed. The source material is configured to produce gamma photons greater than or equal to 6.8 MeV during neutron capture. The solid state radiation detector comprises a Schottky diode and an emitter layer comprising a Compton and photoelectron source material. The emitter layer is configured to receive the gamma photons produced by the source material. The emitter layer is spaced apart from the Schottky diode a distance such that a gap is defined between the emitter layer and the Schottky diode. The distance is selected such that only electrons produced by the emitter layer as a result of the emitter layer absorbing the gamma photons will contribute to a measured output signal of the Schottky diode.

The application discloses a kind of system and method for promoting TOF-PET system counting rate.The system includes a data processing module and multiple acquisition units, each acquisition unit includes a detector module and an electronics module;Detector module is used to detect the gamma photon pair generated by positron annihilation in the detected object, and the nuclear signal generated according to the detected gamma photon pair is converted into electrical signal input electronics module;Electronics module selects the input electrical signal to obtain real coincidence event for acquisition;Data processing module is used to receive the same coincidence time window as a pair of real coincidence events with two real coincidence events, calculate the time difference of two real coincidence events in each pair of real coincidence events to its corresponding detector module, and determine the position of the detected object according to the statistical result of the time difference of each pair of real coincidence events.Theoretical effective counting rate can be improved several times or even an order of magnitude, which greatly improves the sensitivity of the system.

The super-hole collimator for gamma photon detection and the nuclear medicine imaging system provided by the utility model are provided with the collimator plate, the plurality of collimating holes which are irregularly distributed or randomly distributed are formed in the collimator plate, and when radioactive rays in an imaging view pass through the collimating holes and then form projection overlapping on a gamma photon detector, the radioactive rays are irradiated by the gamma photon detector. The orientation of the collimation hole should meet the requirement that the normal vector of the central plane of the collimation hole passes through the center of the imaging view, and the field angle of the collimation hole should meet the requirement that the extension lines of the two edges of the collimation hole are tangent to the imaging view. According to the multi-pinhole collimator, the limitation of a pinhole arrangement mode in a traditional multi-pinhole collimator on the number of pinholes is effectively overcome, a certain number of collimation holes are randomly arranged on the collimator, and the number of the collimation holes is far larger than that of the pinholes in the existing multi-pinhole collimator; the projection overlapping area of radioactive rays on the detector after passing through all the collimation holes in the imaging view field is improved, a super-hole collimator is formed, and the detection efficiency is remarkably improved on the premise that the image resolution is guaranteed.

The present invention discloses a method for detecting the flow field of an aero-engine inlet duct based on a positron annihilation technology. The method comprises the following steps: installing a wind tunnel tube in an annular gamma photon detector, installing a fairing at one end of the wind tunnel tube away from the annular gamma photon detector, and connecting one end of the wind tunnel to a wind tunnel blower; arranging an inlet duct bracket in the wind tunnel tube; fixing the inlet duct to be detected on the inlet duct bracket; planting cotton threads on a silica gel plate in a linear array manner; preparing a radionuclide-labeled aqueous solution to be adsorbed on the cotton threads; fixing the silica gel plate in an inner cavity of the inlet duct to be detected; starting the wind tunnel blower, collecting gamma photon pairs generated by positron annihilation on the cotton threads in the inlet duct through the annular gamma photon detector, and storing the collected gamma photon pairs as three-dimensional sinusoidal graphs; performing interpolation processing on the three-dimensional sinusoidal graphs to expand data; and performing three-dimensional image iterative reconstruction based on the processed three-dimensional sinusoidal graphs to obtain a clear flow field state in the inner cavity of the aero-engine inlet duct.

The invention discloses a positron annihilation parameter spectrogram measuring system and method. The system comprises a positron source, n coding matrixes, a single-pixel detector and an atlas reconstruction module, the positron source is used for emitting an initial positron beam X to the coding matrix; the coding matrix is used for modulating the initial positron beam X to form a modulated positron source Y which is incident on a sample target; the single-pixel detector is used for detecting energy, time or direction of gamma photons generated after each modulated positron source enters the sample target to obtain a corresponding positron annihilation spectrum P and sending the positron annihilation spectrum P to the atlas reconstruction module; and the atlas reconstruction module is used for calculating positron annihilation spectrums Q of sample target areas corresponding to matrix elements allowing positron particles to pass through in each coding matrix according to the n positron annihilation spectrums P, and then generating a positron annihilation parameter spectrogram of the sample target according to a positron annihilation spectrum Q set.

The invention provides a cascade gamma photon coincidence imaging system reconstruction data preprocessing method and system, and belongs to the technical field of nuclear medicine imaging. The method comprises the following steps: firstly, preliminarily screening collected events based on a preset time window, an energy window and a collimator type to obtain an initial coincidence event set; then, back projection is carried out on coincidence events, and parallel invalid events are eliminated by calculating the spatial geometrical relationship between a back projection line model and a back projection plane; secondly, calculating coordinates of an intersection point of the back projection line and the back projection plane, and screening out events of the intersection point in the view field; thirdly, calculating the probability that the voxel where the intersection point is located generates the gamma photon pair, and excluding events with the probability being zero; thirdly, adding one to a voxel count value corresponding to the intersection point, and taking a voxel number as a position mark of the event; and finally, performing final screening based on the voxel count value and a preset threshold. Through a multi-stage screening mechanism, random coincidence events, scattering coincidence events and noise data are eliminated, and the image reconstruction quality of the system is remarkably improved.

The invention provides a multimode iterative reconstruction method and device, and relates to the technical field of nuclear radiation detection. The method comprises the following steps: acquiring event information of interaction between gamma photons and a three-dimensional position sensitive semiconductor detection unit in a panoramic gamma camera system; based on the prior energy, the Compton scattering event count in the event information and the photoelectric absorption event count in the event information, obtaining an information amount, and calculating a weight according to the information amount; compton sequence reconstruction is carried out based on prior energy, and a multimode system transmission matrix is constructed according to the reconstructed Compton sequence; and performing multi-mode iteration reconstruction based on the weight and the multi-mode system transmission matrix, outputting a stable high signal-to-noise ratio image, and determining the spatial distribution of the radioactive source. According to the multi-mode iteration reconstruction method based on the coding aperture combined with the Compton and non-collimation technology, the problems that in traditional multi-mode gamma imaging, the reconstruction resolution ratio is poor, and the imaging signal-to-noise ratio is unstable are solved, and the imaging energy range, the imaging view field and the resolution ratio are effectively improved.