71 results about "Gamma ray detectors" patented technology

Disclosed is a nanosecond neutron analysis and associated particle imaging system (NNA / API) and gamma ray detector arrangement (arrangement) that uses associative element detection of titanium, iron and oxygen to determine concentrations of ilmenite or other minerals in extra-terrestrial bodies associated with He-3. The arrangement is used with a mobile carrier for mapping out concentrations of likely He-3 regions on the extra-terrestrial body.

A PET scanner includes gamma-ray detector rings that form a bore through which an imaging subject is translated, a length of the bore defining an axial length of the PET scanner, the gamma-ray detector rings being movable along the axial length, the gamma-ray detector rings including gamma-ray detector modules therein, and processing circuitry configured to receive PET data associated with a plurality of transaxial slices of the imaging subject, the PET data including a first set of spatial information and timing information corresponding to a first data acquisition period for the gamma-ray detector modules in a first axial position and a second set of spatial information and timing information corresponding to a second data acquisition period for the gamma-ray detector modules in a second axial position, and reconstruct a PET image based on the first set of spatial and timing information and the second set of spatial and timing information.

A downhole tool is provided with a neutron generator configured to emit neutrons into a geological formation. The downhole tool includes one or more neutron detectors configured to detect neutrons that return to the downhole tool after interacting with the geological formation. The downhole tool also includes one or more gamma ray detectors configured to detect gamma rays from the geological formation that form when neutrons are inelastically scattered by the geological formation. Measurements from a combination of detectors of at least one of the one or more neutron detectors and at least one of the one or more gamma ray detectors are used to determine formation density. A first formation density determined using a first combination of detectors is used to compensate a second formation density determined using a second combination of detectors.

A system may include one or more downhole tools, where a first downhole tool includes a pulsed neutron generator to emit neutrons into a borehole of a geological formation and one or more gamma-ray detectors to obtain a measurement of gamma-ray emissions, of a borehole environment, induced by the emitted neutrons. The system may also include data processing circuitry to determine a Sigma value associated with the borehole environment based on the measurement and determine elemental concentrations, excluding lithium, based on one or more gamma-ray energy spectra obtained via the one or more downhole tools. The data processing circuitry may also determine an elemental Sigma contribution of the elements other than lithium based on the elemental concentrations, determine a lithium Sigma contribution based on a difference between the Sigma value and the elemental Sigma contribution, and determine a lithium concentration within the borehole environment based on the lithium Sigma contribution.

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.

Techniques of performing gamma ray coincidence detection are provided. The techniques include identifying, using a first voltage data signal obtained using at least one gamma ray detector disposed adjacent to a sample material, a first time value corresponding to a leading edge of the first voltage data signal and identifying, using a second voltage data signal obtained using the at least one gamma ray detector, a second time value corresponding to a leading edge of the second voltage data signal. The techniques further include determining, using the first and second time values, a time difference value and determining whether the time difference value is greater than or less than a threshold coincidence value to identify whether the sample material underwent a sequential radiative transition.

The invention relates to the technical field of nondestructive testing of element content and uniformity of fuel elements, and provides a fuel element detection method and system based on neutron imaging and activation analysis. The detection method comprises the following steps: S1, installing a to-be-detected sample, and adjusting an imaging collimation hole to be aligned with a neutron beam current of a neutron source; s2, the thermal neutrons are collimated by the imaging collimation hole and then transmit the to-be-detected sample, and spatial distribution of uranium and poison elements of the to-be-detected sample is obtained through detection of a neutron imaging detector; s3, selecting a specific target area, switching the activation analysis collimation hole to align to a neutron beam of the neutron source, and adjusting the position of the to-be-detected sample, so that the specific target area aligns to the neutron beam of the neutron source; thermal neutrons bombard a specific target area after being collimated by the activation collimation hole, and are received by the gamma ray detector so as to analyze and obtain the element content of the specific target area. According to the method, distribution and content of uranium and toxic elements in the fuel element can be rapidly and accurately determined on the premise of nondestructive testing.

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.

The application discloses a water body radioactivity online monitoring system and a monitoring method, and relates to the technical field of water body radioactivity monitoring. The monitoring system comprises a probe device, a probe driver and signal processing device and a data processing device. The probe device comprises a beta particle detector and a gamma ray detector, and is used for detecting beta particles and gamma rays in a water body and outputting detection signals. The probe driver and signal processing device is electrically connected with the beta particle detector and the gamma ray detector, and is used for receiving the detection signals, processing the detection signals and outputting detection data. The data processing device is electrically connected with the probe driver and signal processing device, and is used for receiving the detection data and analyzing the detection data to obtain a monitoring result. The system provided by the application can realize online real-time monitoring of water body radioactivity, and can realize monitoring of water body nuclide content and identification of nuclides.

Methods and apparatus are disclosed for concurrent digital autoradiography of alpha-particle events and positron events using a spatially resolving charged particle detector and a gamma-ray detector. Alpha particles and positrons are detected by the charged particle detector. Positrons are identified based on coincidence with gamma-ray events. A positron-emission autoradiograph is formed based on positron positions. Alpha particles, both coincident and anticoincident with positrons, are identified based on energy deposition patterns. An alpha-emission autoradiograph is formed based on alpha-particle positions and energies. Separation of coincident alpha and positron events recorded by the charged particle detector improves position detection accuracy. Validation of positron imaging for alpha-emitter distribution or dosage, based on correlation of respective autoradiographs, is described. Variations for particle identification based on isotropy, energy, coincidence, or anticoincidence are presented. Disclosed techniques are applicable to alpha-emitting radionuclides with complex decay chains.

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

To provide both good time-of-flight resolution and interaction depth information. [Solution] The positron emission tomography apparatus according to the embodiment comprises a scintillation array and a photosensor array. The scintillation array includes a plurality of scintillator crystal units individually separated by a reflective material, and each scintillator crystal unit is configured to generate scintillation light in response to gamma-ray interactions within the scintillator crystal unit caused by gamma-ray irradiation from a subject, and has a substructure for decoding two or more depths within the scintillator crystal unit such that gamma-ray interactions at different depths cause scintillation light to escape from the photo-escape plane of the scintillator crystal unit in different patterns. The photosensor array converts the scintillation light received from the scintillation array into an electrical signal.

The utility model relates to the field of medical instruments, in particular to a quick-release gamma ray detector probe which comprises a handle and a probe body. The handle comprises a handle body and a control panel, the control panel is arranged on the side face of the handle body, and the control panel is used for controlling the probe to conduct gamma ray detection analysis; the front end of the handle is provided with a Remo joint socket; the probe comprises a Remo joint plug, a fixed long rod and a probe; long rods with included angles are arranged at the two ends of the fixed long rod; the Remo joint plug is arranged at the tail part of the fixed long rod, and the probe is arranged at the front end of the fixed long rod; the Remo joint socket and the Remo joint plug are matched with each other; the probe is connected to the Remo connector plug through a wire arranged in the fixed long rod, and is finally connected to the control panel through cooperation of the Remo connector plug and the Remo connector socket. The probe is convenient to disassemble and split, and can be quickly disinfected before sentinel lymph node detection.

The invention relates to the technical field of radiation detection, in particular to a gamma ray detector and a gamma ray detection system. The detector comprises a substrate, a shading shell, a scintillation crystal, a silicon photomultiplier tube array, a first reflecting layer and a second reflecting layer, the shading shell is connected with the substrate so as to define an open inner cavity with the substrate; the scintillation crystal is located in the open inner cavity; the silicon photomultiplier tube array is located in the open inner cavity and is coupled with the scintillation crystal through an adhesive, and the silicon photomultiplier tube array is connected with the substrate to obtain electric energy; the first reflecting layer is arranged around the scintillation crystal; and the second reflecting layer is connected with a cavity opening of the open inner cavity to form a sealing structure. The invention has the advantages of magnetic interference resistance, miniaturization and high counting rate.

The nuclear medicine diagnostic apparatus of the embodiment includes a processing circuit. The processing circuit obtains simultaneous counting data including direct incident events to a gamma-ray detector and scattered events in an object; obtains the electron density function of the object and geometric information of the gamma-ray detector; infers a first probability value corresponding to the direct incident event of the object and a second probability value corresponding to the scattered event based on at least one of the electron density function and the geometric information; reconstructs a PET image based on the first probability value, the second probability value and the simultaneous counting data. The processing circuit reconstructs the PET image based on a system matrix based on the first probability value and the second probability value.

For gamma ray detection, 3D tiling is made possible by modules (30) that include a gamma ray detector (10) with at least some electronics (12) extending away from the detector (10) as a side wall, leaving an air or low attenuation gap (14) behind the gamma ray detector (10). The modules (30) may be stacked to form arrays of any shape in 3D, including stacking (92) to form a Compton detector (10) with a scatter detector (10) separated from the catcher detector (10) by the low attenuation gap (14) where the electronics (12) form at least one side wall between the detectors (10). The modules (30) may be stacked so that the detectors (10) from the different modules (30) are in different planes and / or not part of a same surface (e.g., same surface provided with just 1D or 2D tiling).

The invention discloses a portable low-energy ray detection device and a preparation method thereof, and belongs to the technical field of radiation monitoring. The device aims at solving the problems that a traditional X or gamma ray detector is large in size, high in cost, complex in operation and insufficient in low-energy ray detection sensitivity. According to the technical scheme, an optical fiber probe module is composed of an optical fiber core, a cylindrical aluminum foil mold and a composite scintillator layer, a Cs3Cu2I5: Mn < 2 + > 15% scintillator material and UV glue mixture is injected into an annular cavity of the mold and cured to absorb low-energy X or gamma rays and emit fluorescence, and the cylindrical aluminum foil mold serves as a reflecting layer; the optical fiber probe module is packaged through a 3D printing optical fiber cap, and the output end is coupled with the photocell to realize photoelectric conversion; the alarm circuit control module adopts a triode control circuit to drive a light emitting diode to emit light. The device is small in size, low in cost and suitable for real-time monitoring and alarming of low-energy rays in environments such as medical radiation departments and the like, and personnel safety is guaranteed.

Neutron-induced radiation detectors (NiRDs) and radiation dosimetry systems containing the same are described. Examples of NiRDs can include numerous components based on location, function, dimension, and / or constituent materials. A NiRD can be configured to directly measure an absorbed dose (or rate) of particular ionizing reaction products induced by neutrons. The NiRD can utilize various detection schemes for measuring the deposited energy of the reaction products, such as gaseous ionization, semiconducting, scintillating, or homogenous versions of these detection schemes. The NiRD can measure the deposited energy of the reaction products in forward emission, backward emission, or both. Examples of radiation dosimetry systems can include one or more NiRDs, a gamma ray detector, and readout electronics coupled to each of the radiation detectors. Example implementations of the radiation dosimetry systems are described for determining an equivalent dose (or rate) of a neutron beam generated for boron neutron capture therapy (BNCT).

A downhole tool is provided with a neutron generator configured to emit neutrons into a geological formation. The downhole tool includes one or more neutron detectors configured to detect neutrons that return to the downhole tool after interacting with the geological formation. The downhole tool also includes one or more gamma ray detectors configured to detect gamma rays from the geological formation that form when neutrons are inelastically scattered by the geological formation. Measurements from a combination of detectors of at least one of the one or more neutron detectors and at least one of the one or more gamma ray detectors are used to determine formation density. A first formation density determined using a first combination of detectors is used to compensate a second formation density determined using a second combination of detectors.

A gamma ray measurement tool has a tubular shell, a gamma ray detector disposed in the tubular shell, and a shield disposed between the tubular shell and the gamma ray detector. The gamma ray detector has a scintillation crystal coupled to a photomultiplier tube, and the shield has a open window configured to allow gamma rays to pass through and reach the scintillation crystal. Further, the tubular shell has a first axis in the longitudinal direction, and the gamma ray detector has a second axis in the longitudinal direction, the first axis and the second axis do not coincide with each other, and a distance between the scintillation crystal and an inner surface of the tubular shell through the window is shorter than a distance between the scintillation crystal and a portion of the tubular shell covered by the shield.

The invention particularly relates to a combined detector for an online sipping device. The combined detector comprises a beta-ray detector, a gamma-ray detector and a signal processing system, the beta ray detector adopts a plastic scintillation chamber with a high beta / gamma response ratio; the gamma ray detector adopts a scintillation crystal; the signal processing system is configured to perform beta-gamma coincidence measurement on output signals of the beta-ray detector and the gamma-ray detector; the plastic scintillation chamber is adjacent to the scintillation crystal space, and the detection areas of the plastic scintillation chamber and the scintillation crystal space are at least partially overlapped so as to jointly detect the detected gas flowing through the plastic scintillation chamber. The invention further relates to a nuclear fuel assembly damage detection method which adopts the combined detector. According to the invention, comprehensive detection of beta and gamma rays of radioactive inert gas is realized, and efficient and sensitive measurement of beta rays in large-volume radioactive inert gas is realized, so that the efficiency and accuracy of gamma-beta coincidence measurement are improved.

The present invention discloses an element distribution imaging device and method based on a rotary modulation collimator. The measuring device comprises a neutron generator, a rotary modulation collimator, a gamma ray detector and a data acquisition and processing system. The rotary modulation collimator comprises two encoding plates, a cylinder, a synchronous belt and a motor. The sample to be tested is placed in a neutron field between the neutron generator and the rotary modulation collimator. The elements to be tested in the sample to be tested react with the neutrons in the neutron field and emit characteristic gamma rays of different energies through capture reaction and inelastic scattering. The characteristic gamma rays change in flux after passing through the encoding plate. The gamma ray detector measures the characteristic gamma rays after the flux changes. The gamma ray detector is connected to the data acquisition and processing system. The gamma ray detector can send the measured characteristic gamma ray data to the data acquisition and processing system. The present invention has the advantages of high detection accuracy, high detection efficiency and short measurement time.

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.

The present invention provides a gadolinium-based neutron / gamma discrimination system, comprising a gadolinium-based neutron detector, a gamma-ray detector, a preamplifier circuit connected to the detector, and a dual-channel digital multichannel spectrometer. The dual-channel digital multichannel spectrometer receives two pulses amplified by the preamplifier circuit. When the time difference between the arrival times of the two pulses is within a set threshold, the system counts neutron signal events and further extracts amplitude values, recording them in the neutron response energy spectrum and gamma energy spectrum, respectively. The present neutron / gamma discrimination system combines physical processes with electronic technology. A thin sheet of gadolinium-based material absorbs only internal conversion electrons and low-energy background gamma rays. The system then uses the temporal relationship between internal conversion electrons and secondary prompt gamma rays to further distinguish whether the signal detected by the gadolinium-based material sheet is internal conversion electrons or low-energy background gamma rays, thereby achieving neutron / gamma discrimination.

The invention discloses a tomography device and method for continuously adjusting gamma ray energy in a large range, and solves the problem that gamma rays for CT imaging cannot clearly image all components with different densities in an object. The gamma ray detector specifically comprises a gamma ray source, a first-stage collimation shielding body, a first-stage scatterer, a second-stage collimation shielding body, a second-stage scatterer, a shaping shielding body and a detection unit, the gamma ray source is located outside an entrance port of the first-stage collimation shielding body; the primary scatterer is positioned outside the incident port of the secondary collimation shielding body and corresponds to the emergent port of the primary collimation shielding body; the shaping shielding body is arranged at the bottom of the secondary collimation shielding body, and the top is provided with a radiation gap; an incident port of the radiation gap is communicated with an emergent port of the secondary collimation shielding body; the secondary scatterer is positioned in an incident port of the radiation gap and is also positioned outside an emergent port of the secondary collimation shielding body; the detection unit is located on the side face of the shaping shielding body and used for detecting the gamma ray intensity value of the gamma rays emitted from the radiation notch after the gamma rays are transmitted through the to-be-imaged object.

Proposed are a gamma ray probe capable of being inserted into the human body and a gamma ray detection apparatus using the same. The gamma ray probe includes a collimator, a scintillator array disposed on a rear of the collimator and configured to emit light photons in response to radiation passing through the collimator, a light sensor module disposed on a rear of the scintillator array and configured to detect light photons emitted from the scintillator array and convert the light photons into an electrical signal, a light guide part disposed between the scintillator array and the light sensor module and configured to guide light photons from the scintillator array to the light sensor module, and a cylindrical probe casing accommodating the collimator, the scintillator array, the light sensor module, and the light guide part therein.

The invention discloses a gamma logging instrument principle demonstration simulation device and method, and belongs to the field of logging principle demonstration. The apparatus includes a cylinder for simulating a formation model; the cylinder is vertically arranged, and different light transmission properties are achieved at different heights of the cylinder; a photoresistor device is arranged in the cylinder and is used for flatly replacing the gamma ray detector; the photoresistor device is connected with a driving device for driving the photoresistor device to move up and down; the photoresistor device is further connected with the linear voltage-controlled oscillator through a wire, the linear voltage-controlled oscillator is connected with the voltage comparator, the voltage comparator is connected with the counter, and the counter is connected with the single-chip microcomputer. Different illumination intensities can be converted into electric pulse signals with different frequencies, square wave pulses output by the voltage comparator in unit time are counted through the counter, and gamma logging simulation is achieved. The structure and the scale of the measuring device and the simulated stratum in the demonstration process are simplified, and the convenience and the intuition of related demonstration operation are enhanced.

The invention provides a ray deposition process Boolean operation-based X / gamma ray detector passive efficiency scale calculation method, which belongs to the technical field of nuclear radiation measurement, and comprises the following steps: dispersing a radioactive source into a plurality of point radioactive sources in space, and obtaining ray angle distribution; analyzing to obtain the passing distance of the ray in the shielding body; calculating to obtain a line absorption coefficient; calculating the attenuation proportion of the shielding body; acquiring a ray deposition process in the sensitive body to form a scattering point coordinate matrix; performing coordinate system transformation on the ray deposition process to obtain a scattering point model, and performing graphic Boolean intersection operation on the scattering point model and the sensitive body; calculating the intrinsic detection efficiency of the rays; and calculating the radioactive source detection efficiency according to the ray angle distribution, the attenuation ratio and the intrinsic detection efficiency. According to the technical scheme provided by the invention, rapid and accurate passive efficiency calibration can be carried out, and a reliable and efficient solving technology is provided for large-volume long-distance radioactive source calibration.

The invention relates to the technical field of radioactivity measurement, in particular to radioactivity on-line monitoring of mineral products such as coal and iron ore, which comprises a radioactivity detection module for radioactivity on-line monitoring, an alarm output module when the radioactivity intensity of the mineral products exceeds the standard, and a measurement and control module for realizing measurement control, the radioactivity detection module is provided with a gamma ray detector; the radioactivity detection module is installed above a mineral product conveying line; the whole set of system is further provided with a positioning module to realize mineral product radioactive intensity standard exceeding positioning, and is provided with a nuclide identification module to realize nuclide type identification. A gamma dose equivalent rate module is configured to measure the dose equivalent rate; the problem that an existing online radioactivity monitoring system cannot be used for online radioactivity monitoring of mineral products is solved, and online radioactivity monitoring of the mineral products is achieved.

Systems and methods presented herein support porosity estimation using neutron-induced gamma ray spectra. For example, the systems and methods presented herein include receiving, via a control and data acquisition system, data relating to an energy spectrum of gamma rays captured by one or more gamma ray detectors of a neutron-induced gamma ray spectral logging tool. The method further includes deriving, via the control and data acquisition system, one or more spectral yields related to one or more elemental components from the data related to the energy spectrum of the gamma ray. The method further includes estimating, via the control and data acquisition system, a measurement of porosity based on the one or more spectral yields associated with the one or more elemental components.