22 results about "Gamma ray detection" patented technology

The present invention provides a TSV radiation-resistant packaging structure and a packaging method. The TSV radiation-resistant packaging structure comprises: a first redistribution layer, which is disposed on a front side of a wafer; the wafer, a cavity being etched inside the wafer; a chip, which is disposed in the cavity inside the wafer; a second redistribution layer, which is disposed on a back side of the wafer and is electrically connected to the chip; a radiation protection layer, which is disposed in the cavity inside the wafer and on the back side, and encapsulates the chip; and a TSV via, which penetrates through the wafer and connects the first redistribution layer to the second redistribution layer. A radiation-resistant material is used to protect the chip, such that the present invention can be used in fields such as high-energy X-ray detection and gamma-ray detection, thereby improving the protection performance of the chip.

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 application discloses a casing-after-density inversion calculation method and device, equipment and a storage medium. According to the technical scheme provided by the application, the nuclear radiation particle transport process of the downhole gamma ray is simulated, a detector count ratio matrix is constructed, and a target function is constructed according to the detector count ratio matrix; the detector is used to detect the gamma ray of the casing well, and actual detection data of the detector is obtained; the actual detection data is substituted into the detector count ratio matrix to obtain a first count ratio function, and standard detection data under a standard condition is substituted into the detector count ratio matrix to obtain a second count ratio function; the target function is solved by using the first count ratio function and the second count ratio function, and the formation density and the cement density are determined. According to the application, the standard detection data and the actual detection data can be used to perform inversion based on the target function, and the formation density and the cement density can be accurately obtained.

A medical imaging apparatus based on gamma-ray detection includes a detector and circuitry. The detector includes a plurality of detector modules. Each detector module is divided into N light-sharing segments, and each light-sharing segments covers M photosensors. The circuitry includes (1) a plurality of sets of M first-level electronic units and (2) a second-level electronic unit. Each set of M first-level electronic units reads the electrical signals generated by of a corresponding one of the plurality of detector modules. For each detector module, each first-level electronic unit of a corresponding set of M first-level electronic units reads the electrical signals generated by N photosensors, in a multiplexing manner, to generate timing, energy, and position readout signals on a single set of readout channels. The second-level electronic unit processes the timing, energy, and position readout signals output from M sets of readout channels of the set of M first-level electronic units.

This invention discloses a method for preparing a multi-level micro / nano-structured composite material for nuclear radiation detection, relating to the field of nuclear radiation detection technology. Specifically, it utilizes gold-sulfur self-assembly technology to modify the surface of a gold nanoparticle core with boron-containing molecules, obtaining a functionalized gold nanoparticle core. This core is then used as a seed, with chloroauric acid as the gold source, to grow a gold nanoshell. Finally, silver nitrate is used as the silver source to deposit a silver nanoshell in situ, resulting in a multi-level micro / nano-structured composite material. This multi-level micro / nano-structure uses gold nanoparticles as the core, boron-containing molecules as the neutron detection medium, the gold nanoshell as the surface-enhanced Raman scattering (SERS) carrier, and the silver nanoshell as the gamma-ray detection medium. This material possesses both neutron and gamma-ray detection capabilities, and the neutron response of the boron-containing molecules and the gamma-ray response of the silver nanoshell can be quantitatively measured using SERS and LSPR spectroscopy, respectively. This enables efficient discrimination of mixed radiation field doses and has broad application prospects in the field of nuclear radiation detection.

Aspects of the disclosure relate to a method for understanding the response of any multi-detector device to activated oxygen. The method relies on an expression of a three-dimensional distribution of activated oxygen from fast neutron, and on the expression of three-dimensional gamma ray detection efficiency. A realistic model is derived for the signals measured in the detectors as function of the device-to-oxygen differential velocity.

Aspects of the disclosure relate to a method for understanding the response of any multi-detector device to activated oxygen. The method relies on an expression of a three-dimensional distribution of activated oxygen from fast neutron, and on the expression of three-dimensional gamma ray detection efficiency. A realistic model is derived for the signals measured in the detectors as function of the device-to-oxygen differential velocity.

The application discloses a circular laminated collector gamma ray detection ionization chamber, which comprises an ionization chamber shell, a collector, an insulator and an ionization chamber base, the bottom of the ionization chamber shell is connected with the ionization chamber base, and the whole forms a cylindrical type, the insulator is installed at the center of the ionization chamber base, the collector comprises three collector rings, the collector rings are coaxial with the ionization chamber shell and are arranged in an axial direction, the three collector rings are connected through connecting rods on two sides, the collector ring at the bottom is connected with an extraction electrode, the extraction electrode extends out of the insulator and is connected with a cable connector. The gamma ray detection ionization chamber improves the measurement of radiation dose rate and measurement accuracy.

The application discloses a neutron gamma detector with high dynamic range and time resolution, comprising: a plurality of layers of detection units, a plurality of neutron moderators and a detector shell; each detection unit is arranged along the axis of the detector shell, and a neutron moderator is arranged between each detection unit; the detection unit comprises a neutron / gamma sensitive scintillator array, a photomultiplier tube array and a preamplifier array, and each layer of neutron / gamma sensitive scintillator array is matched with one layer of photomultiplier tube array and one layer of preamplifier array. The detector utilizes the multiple layers of neutron moderators to form the gradient of the neutron and gamma ray detection efficiency of each layer of scintillator, the neutron / gamma sensitive scintillator array matched with the photomultiplier tube array and the preamplifier array can measure and obtain a pulse count matrix, and then the neutron and gamma count rate at each layer of detector can be extracted. Meanwhile, the time resolution and dynamic range are improved based on the structural design of the detector.

The invention discloses a method and a system for monitoring the material level of an electric precipitation ash hopper based on a multi-probe passive nucleon material level indicator, and the system comprises passive nucleon probes, a data processing unit, a data analysis unit, a data storage unit and a management control unit, the passive nuclear probe is respectively in communication connection with the data storage unit, the data processing unit and the management control unit, the data processing unit is respectively in communication connection with the data storage unit, the data analysis unit and the management control unit, and the data analysis unit is respectively in communication connection with the data storage unit and the management control unit. According to the method, the multi-height gamma ray detection signals are subjected to conjoint analysis, the space accumulation characteristics of the fly ash in the ash bucket are identified, and the equivalent material level height of the ash bucket is constructed on the basis, so that the material level monitoring reliability under the non-uniform accumulation working condition is improved.

The utility model relates to a gamma-ray detection probe which comprises a gamma-ray sensor, a sensor mounting seat, an electrical box and a signal processing board, the sensor mounting seat is fixedly connected with the electrical box; and a plurality of gamma-ray sensors are arranged, the plurality of gamma-ray sensors are embedded in the sensor mounting seat, and the plurality of gamma-ray sensors are uniformly distributed in a circumferential manner. The gamma-ray sensors are electrically connected with the signal processing board respectively; the signal processing board is used for being electrically connected with the single-chip microcomputer. The signal processing board is detachably fixed in the electrical box. When the gamma ray detection probe is used in cooperation with a single chip microcomputer, the single chip microcomputer can obtain the radiation intensity monitored by each gamma ray sensor, and a straight line formed by connecting the gamma ray sensor with the maximum radiation intensity and the gamma ray sensor with the minimum radiation intensity is the emission direction of gamma rays. The gamma ray detection probe component can judge whether gamma rays exist or not and can judge the source direction of the gamma rays.

It is an object to provide a device and a method for x-ray and / or gamma ray detection. According to an embodiment, a device comprises: a detector comprising a plurality of pixels, wherein the plurality of pixels comprises a first subset of pixels configured to detect incident x-ray or gamma ray radiation in a first energy range and a second subset of pixels configured to detect incident x-ray or gamma ray radiation in a second energy range; a processing unit configured to: obtain a signal from each pixel in the plurality of pixels; obtain a radiation intensity value for each pixel in the plurality of pixels based on the signal of each pixel; calculate a radiation intensity estimate in the first energy range for at least one pixel in the second subset of pixels. A device and a method are provided.

The invention provides an underground natural gamma counting intensity detection device and method, and belongs to the technical field of oil-gas exploration, and the device comprises a perovskite semiconductor detector which is used for directly absorbing gamma rays from a stratum and generating corresponding electric signals, the perovskite semiconductor detector comprises a sensitive body made of a perovskite semiconductor material, and the sensitive body directly absorbs gamma rays and generates electron-hole pairs; the signal processing circuit is electrically connected with the perovskite semiconductor detector and used for processing the electric signals to obtain measurement data related to gamma ray intensity, and by means of the underground natural gamma ray detection device and method, the efficiency and accuracy of underground natural gamma ray detection can be improved.

The utility model relates to a double-beta plastic scintillator detector based on SiPM readout. The double-beta plastic scintillator detector comprises two hollow plastic scintillators, a SiPM array and a corresponding signal readout circuit, an inflation pipeline, a valve, a reflecting film and a light shielding layer. The two hollow plastic scintillators are stacked away from light; the SiPM array is coupled to the side surface of the hollow plastic scintillator, and the signal-to-noise ratio of the detector is improved by using the SiPM array partition according with the noise reduction technology; the two hollow plastic scintillators pasted with the reflecting films and the light shielding layers are packaged in a stainless steel shell to form a dual-channel beta plastic scintillator detector so as to realize synchronous high-sensitivity measurement of different radioactive gases. According to the utility model, the two hollow plastic scintillators are packaged into the double-beta detector, so that synchronous high-sensitivity measurement of different radioactive gases can be realized. The SiPM is assembled on the side wall of the scintillator, and two oppositely arranged gamma detectors can be adopted for measurement, so that the gamma ray detection efficiency is improved, and the detection sensitivity is further improved.

A device for the detection of gamma rays to be used primarily in a PET scanner is based on a scintillator heterostructure combining the high stopping power of scintillators commonly used in PET scanners (such as L(Y)SO, BGO, etc.) and fast scintillators based on polymers loaded with fast emitting dyes or nanocrystals, or thin layers of nanocrystals or multiple quantum well structures. While the metascintillator block is read out in the monolithic or semi-monolithic arrangement, the fast scintillator is segmented so that it is read out by less photodetectors. The particular arrangement of this detector module allows combining all the important features of a high-performance Time-of-Flight PET (TOFPET) detector module, i.e. a high photoelectric detection efficiency for the gamma rays, a precise 3D information (including the depth of interaction DOI) of the gamma ray conversion in the module, good energy resolution and superior timing resolution.

The invention provides a four-quadrant gamma ray detector and a gamma ray orientation method, and the detector comprises four gamma ray detection units with the same structure, the four gamma ray detection units are arranged in a 2 * 2 array, and each detection unit works independently and is used for converting an incident gamma ray into an electric signal; and the data acquisition and processing system is used for controlling a data acquisition time sequence and executing conformity judgment and selection logic and gamma ray direction resolving. The invention has the advantages that direction sensitive detection is realized through the four-quadrant array structure, and compared with the traditional collimator scheme, the weight is reduced by more than 70%; conventional background measurement and transient event capture are taken into account in a four-channel composite acquisition mode; the orientation algorithm based on the relative intensity ratio does not need absolute calibration, and the on-orbit calibration complexity is reduced. Tests show that the 1 MeV gamma ray orientation precision is superior to 5 degrees (half angle), and the requirements of space science exploration tasks are met.

The utility model relates to a radioactive gas beta ray measuring device based on SiPM. The radioactive gas beta ray measuring device comprises an inflation pipeline, a SiPM array, a source box, a light shielding layer and an external packaging structure. The source box is of a hollow sealed structure, a through hole is reserved in a certain side wall of the source box, the source box is connected with the inflation pipeline, and the SiPM array is formed by splicing small-area SiPM units according to the surface shape of the source box and is coupled with the upper surface of the source box; except the surface, coupled with the SiPM array, of the source box, the other outer surface area is covered with a light shielding layer; and the source box is integrally packaged in the external packaging structure. According to the utility model, the miniaturization of the measuring device is realized; the influence of SiPM array dark counting is eliminated, the signal-to-noise ratio of the system is improved, the lower threshold of detection ray energy is reduced, and the detection efficiency of beta rays with continuous energy can be improved. The device is high in gamma ray transmittance, the SiPM array can be assembled on the side wall of the scintillator, the upper surface and the lower surface of the scintillator can be matched with two gamma detectors for detection at the same time, the gamma ray detection efficiency is improved, and the detection sensitivity of the system is further improved.

The application provides a Li + Doped halide scintillation crystal and preparation method thereof, the chemical formula of the scintillation crystal is Cs 1‑x Cu2I3:xLi, wherein the value range of x is 0.001<=x<=0.1. CuI powder, CsI powder and LiI powder are dosed in a molar ratio of 2:(1-x):x under an inert atmosphere, and after being fully mixed, the raw material powder is used to grow the Cs 1‑x Cu2I3:xLi one-dimensional perovskite structure metal halide scintillation crystal by a spontaneous nucleation crucible descending method. The crystal can emit a broadband yellow light of 400-800 nm after excitation, and the intensity is much higher than that of the original pure component crystal. Due to the existence of Li + , the application range is further expanded from the original X / gamma ray detection to the neutron detection field.

The application relates to a linear array gamma ray detector for intraoperative tumor detection and a use method thereof, which comprises an exploration shell and a handle shell, N gamma ray detection units are arranged in a column and at equal intervals along the length direction in the exploration shell, and a gamma ray detection unit at a middle position is a position detection unit W; each gamma ray detection unit is matched with a collimator, the collimating direction is parallel to the axis direction of the handle shell, and the collimating direction of the collimator corresponding to the position detection unit W is coincident with the axis of the handle shell; a displacement sensor and an angle sensor are arranged in the handle shell, a plurality of indicator lamps are arranged on the exploration shell and correspond to the N gamma ray detection units, and the indicator lamps are used for indicating whether the corresponding gamma ray detection units have signal responses; the gamma ray detection units, the displacement sensor, the angle sensor and the indicator lamps are connected with a controller. The technical scheme has the advantages of simple structure, lightness, low cost and convenient use.

The invention relates to an autonomous robot for detecting radiological contamination emanating from a surface, comprising a control unit configured to prescribe (E0, E1, E2, E3, E8) a speed (V) of movement and a measurement time (Fi, Fi+1) for the gamma radiation detection probe, to control (E4) the movement system (2) along a first path (T1) at the speed (V), and to control the probe (4) to measure a first number (M) of detected counts during the time (Fi, Fi+1) during the first path (T1), to calculate (E4) a gamma radiation emission activity (A) as a function of the number (M), and, if the activity (A) is below the prescribed activity threshold (SA), to control the wireless transceiver (5) transmitting (E6) an information (INF1) indicating the absence of detection of radiological contamination; otherwise, to control the transceiver (5) transmitting (E7) an information (INF2) indicating the detection of radiological contamination.Figure for the abbreviation: Figure 4A.