42 results about "Gamma ray detection" patented technology

The invention discloses a fast thermal neutron and gamma ray multi-mode detector, and relates to the technical field of nuclear radiation detection, and the detector comprises a detector housing, and the interior of the detector housing is connected with a fast neutron detection unit, a thermal neutron detection unit and a gamma ray detection unit. The gamma ray detection unit is located between the fast neutron detection unit and the thermal neutron detection unit; and an insulating separation unit is connected between two adjacent detection units. The detector can detect fast neutrons, thermal neutrons and gamma rays in the same equipment at the same time, structures such as a cadmium thermal neutron shielding layer and a fast neutron moderation layer do not need to be added, the size of the detector can be greatly reduced, and the detector has the advantages of being compact in structure, stable in performance, wide in energy measurement range, wide in fluence rate measurement range and the like. The ultrahigh-energy high-flux neutron measurement with the neutron energy at least covering # imgabs0 # and the neutron fluence rate at least covering # imgabs1 # can be realized.

The invention provides a TSV anti-radiation packaging structure and packaging method, and the structure comprises a first rewiring layer which is disposed on the front surface of a wafer; a cavity is etched in the wafer; the chip is arranged in the inner cavity of the wafer; the second redistribution layer is arranged on the back surface of the wafer and is electrically connected with the chip; the radiation protection layer is arranged in the inner cavity and the back surface of the wafer and wraps the chip; and the TSV is arranged on the wafer in a penetrating manner and is connected with the first redistribution layer and the second redistribution layer. The anti-radiation material is used for protecting the chip, and can be applied to the fields of high-energy X-ray detection, gamma ray detection and the like, so that the protection performance of the chip is improved.

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 discloses a neutron gamma detector with a high dynamic range and time resolution. The neutron gamma detector comprises a plurality of layers of detection units, a plurality of neutron moderation bodies and a detector shell, each detection unit is arranged along the axis of the detector shell, a neutron moderator is arranged between every two detection units, each detection unit comprises a neutron / gamma sensitive scintillator array, a photomultiplier array and a pre-amplifier array, and each layer of neutron / gamma sensitive scintillator array is matched with one layer of photomultiplier array and one layer of pre-amplifier array. According to the detector, multiple layers of neutron slowing-down bodies are utilized to form gradients of neutron and gamma ray detection efficiency of each layer of scintillators, and a pulse counting matrix can be measured and obtained after the neutron / gamma sensitive scintillator array is matched with the photomultiplier tube array and the pre-amplifier array. And then neutron and gamma counting rates at each layer of detector are extracted. Meanwhile, based on the structural design of the detector, the time resolution and the dynamic range are improved.

The present invention proposes a three-dimensional reconstruction method for pathological image features of proliferative tricholoma, which relates to the field of three-dimensional reconstruction technology. The method includes: obtaining a pathological slice image and its depth information to generate a pathological slice depth image containing the depth information; emitting laser signals to detect the pathological tissue and extract high-characteristic regions of the pathological tissue; emitting gamma rays to detect the pathological tissue and generate gamma-ray absorption key regions that highlight the tumor region of the pathological tissue; and combining the extracted high-characteristic regions of the pathological tissue with the gamma-ray absorption key regions to supplement the three-dimensional information of the pathological slice depth image to obtain a reconstructed three-dimensional morphology of the pathological image of proliferative tricholoma. The method of the present invention provides detailed anatomical information for subsequent treatment plan formulation.

The invention discloses a preparation method of a multistage micro-nano structure composite material for nuclear radiation detection, and relates to the technical field of nuclear radiation detection. The preparation method comprises the following steps: modifying boron-containing molecules on the surface of a nanogold core by using a gold-sulfur self-assembly technology to obtain a functionalized nanogold core; growing a nano-gold shell by taking the nano-gold shell as a seed and chloroauric acid as a gold source; and finally, silver nitrate is used as a silver source, a nano silver shell is deposited in situ, and the multi-stage micro-nano structure composite material is obtained. According to the multi-stage micro-nano structure, gold nanoparticles serve as an inner core, boron-containing molecules serve as a neutron detection medium, a gold nanoshell serves as a surface-enhanced Raman scattering carrier, and a silver nanoshell serves as a gamma ray detection medium. The material has neutron detection and gamma ray detection capabilities, neutron response of boron-containing molecules and gamma ray response of the nano-silver shell can be quantitatively measured through SERS spectrum and LSPR spectrum respectively, high-efficiency discrimination of the dose of a mixed radiation field can be realized, and the material has a wide application prospect in the field of nuclear radiation detection.

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.

Gamma ray detection system comprising a detection module assembly including at least two detection modules configured for positron emission tomography (PET) scanning of a target zone, each detection module comprising a plurality of stacked scintillator plates each having a major surface oriented to generally face the target zone and lateral minor surfaces defining edges of the scintillator plates, a plurality of photon sensors being mounted against said edges layer photon sensor 18a configured to detect a scintillation event in the scintillator plate from a gamma ray incident on the major surface. The gamma ray detection system is further configured to function as a Compton camera, at least one scintillator plate that is not the scintillator plate closest to the target zone being configured as an absorber scintillator plate for said Compton camera.

The invention discloses a gamma spectrometer and a radionuclide activity measuring method based on the gamma spectrometer. The gamma spectrometer comprises a CZT detector. The CZT detector comprises a CZT probe; the CZT probe comprises a CZT crystal group for receiving gamma rays; and the CZT crystal group comprises at least two CZT crystals. The CZT detector of the gamma spectrometer is more suitable for multi-point online measurement of a radiation source item, the CZT detector comprises the CZT probe, the CZT probe comprises the CZT crystal group used for receiving gamma rays, the CZT crystal group comprises at least two CZT crystals, the effective area of gamma ray detection is increased through the at least two CZT crystals, and the detection efficiency of high-energy gamma rays can be remarkably improved.

To provide, in terms of precision and real-time demand, an innovative technique for measuring the thermal power of a nuclear power plant.SOLUTION: A method comprises: measuring a number of gamma-ray counts in a gamma-ray sensitive detector (60) that is placed outside a biological shield (10) near a primary cooling circuit of a nuclear power plant; and determining the thermal power of the nuclear power plant based on the number of gamma-ray counts measured in the gamma-ray sensitive detector (60).SELECTED DRAWING: Figure 2

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.

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 provides a hyperplastic sheathing tumor pathological image feature three-dimensional reconstruction method, and relates to the technical field of three-dimensional reconstruction, and the method comprises the steps: obtaining a pathological section image and depth information of the pathological section image, and generating a pathological section depth image containing the depth information; emitting a laser signal, detecting a pathological tissue, and extracting a high feature region of the pathological tissue; emitting gamma rays, detecting the pathological tissue, and generating a gamma ray absorption key area highlighting the tumor area of the pathological tissue; and three-dimensional information of the pathological section depth image is supplemented by combining an extracted high-feature region and a gamma ray absorption key region of the pathological tissue, so that the three-dimensional form of the reconstructed hyperplastic sheathing tumor pathological image is obtained. According to the method, detailed anatomical information is provided for subsequent treatment scheme formulation.

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.

1. The name of this design product: Gamma detector probe. 2. Purpose of this design product: This design product is used for gamma ray detection. 3. The design key point of this appearance design product lies in the shape. 4. The picture or photo that best illustrates the design points: Stereoscopic diagram 1.

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 application belongs to the technical field of radiation measurement and scintillation material, and particularly relates to a Eu-doped multi-element halide scintillator and a preparation method and application thereof. 1‑0.5x Ba 1‑0.5x Eu x I 5‑y B y of the Eu-doped multi-element halide scintillator and a preparation method thereof, the scintillator with the chemical composition has excellent energy resolution and light yield, and the preparation method combines raw material solid-phase reaction pre-synthesis, carbon film plating of a quartz crucible and seed crystal directional growth, and successfully realizes preparation of high-quality transparent single crystals. The scintillator provided by the application can be widely applied to the field of radiation detection, such as full-spectrum gamma ray detection.

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.

A PET apparatus includes a detector block including a miniblock including detector crystals, a first detector crystal and a second detector crystal being separated by an inner reflector, the inner reflector having a depth-dependent transparency, a first photosensor configured to detect light from a gamma ray detection event, and a second photosensor configured to detect the light from the gamma ray detection event, a first intensity and a second intensity of the light detected by the first and second photosensor being dependent on the depth-dependent transparency of the inner reflector; and processing circuitry configured to determine, based on the detected first intensity, a first energy, determine, based on the detected second intensity, a second energy, and determine, based on the first energy and the second energy, a depth of interaction (DOI) of the gamma ray detection event.

The invention 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, 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 invention, 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.

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.