12 results about "Czt detector" patented technology

Three-dimensional and quick radiation detection via cadmium-zinc-telluride (CZT) detectors enable intraoperative / intrasurgical imaging and guidance with respect to radioactive objects detected within a patient body. Multiple CZT detectors are located around the patient body. An image reconstruction can be performed based on 3D-sensitive detections by the multiple CZT detectors to detect (e.g., and triangulate) a radioactive object within the patient body. Using a detected location of the radioactive object, a virtual representation of the radioactive object is provided in an extended reality (XR) experience that captures the patient body. A user wearing an XR headset may be provided with the XR experience while interacting with the patient body, for example, during a surgery.

Fission reactions within a molten salt reactor may produce gaseous fission products. These fission products may be removed through a variety of methods. However, proper removal of such fission products requires a thorough understanding of the proportion of gaseous space to fluid space within the component being interrogated, known as the void fraction. The present invention provides a means for determining the void fraction within such a component utilizing an enrich cadmium zinc telluride detector to produce collimated radiation data. The collimated radiation data may then be used to compute a mean void fraction across the domain being interrogated.

The present invention provides a method for preparing a linear array CZT detector, comprising: cutting a crystal into rectangular wafers along the <111> crystal orientation, performing surface treatment to remove surface damage, forming electrode patterns on the {111}Te surface of the wafer, providing scribe lines between the electrode patterns, and performing photolithography followed by gold plating; stripping the gold film on the photoresist, applying photoresist on the {111}Te and {111}Cd surfaces, cutting the wafer into multiple wafers along the scribe lines, and removing the photoresist; placing the multiple wafers in the grooves of a PVD tray fixture, and gold plating the {111}Cd surfaces; applying positive resist to the {111}Te and {111}Cd surfaces of the gold-plated wafers for protection, polishing the four side surfaces, and finally removing the photoresist to complete the preparation. This method solves the problems of edge chipping and missing electrode patterns caused by uneven resist coating, and can prepare multiple linear array detectors at a time, with high production efficiency, low processing costs, simple operation, and strong controllability.

This invention relates to the field of radionuclide detection technology, and more particularly to a portable nuclide identification system based on an array-type CZT detector. The system includes a detector bias high-voltage establishment module, a raw energy spectrum acquisition module, a high-voltage power failure emergency protection module, an analysis thread module, and an energy spectrum UI display module. It achieves uniform high-voltage rise and fall and precise voltage stabilization through PID control, providing a reliable bias for the CZT detector. Simultaneously, it combines an array-type CZT detector with a dedicated ASIC readout circuit to complete high-precision conversion of gamma-ray energy and data verification and transmission. It also accumulates and stores energy spectrum data in real time and enables seamless power switching and soft-voltage shutdown, ensuring hardware, software, and data security. The analysis thread module performs preprocessing, peak fitting, intelligent disassembly of overlapping peaks, and branch ratio verification to complete qualitative identification of nuclides and quantitative analysis of activity concentration. Furthermore, it achieves smooth energy spectrum display through LTTB algorithm downsampling and supports touchscreen interaction and real-time nuclide information annotation.

The utility model discloses a CZT detector test angle response measuring device, which relates to the technical field of semiconductor testing and comprises a base, a fixing mechanism, a measuring cover, a driving mechanism and a plurality of radioactive sources. The fixing mechanism is installed on the base and used for fixing a to-be-tested piece. The measuring cover is hemispherical, is rotationally mounted on the base and is used for covering the fixing mechanism; a plurality of placing holes are formed in the measuring cover and are used for installing radioactive sources in a one-to-one correspondence manner; the driving mechanism is installed on the base, connected with the measuring cover and used for driving the measuring cover to rotate. By means of the design, testing at different angles is achieved, the testing efficiency is improved, and meanwhile comparison parameters of multiple angles can be measured through one device.

The invention provides a simulation database generation method and system based on CZT carrier transport characteristics and energy spectrum characteristics, and relates to the technical field of semiconductors, and the method comprises the steps: simulating energy deposition position distribution data of a radioactive source gamma ray in a CZT detector through GEANT4; constructing a detector electric field model according to the energy deposition position distribution data, and obtaining potential distribution on a carrier drift path; according to the energy deposition value and the energy required for generating a pair of carriers, combining a fano factor to generate an initial carrier number obeying Gaussian distribution; setting a carrier mobility lifetime product parameter, and iteratively calculating capture attenuation in a carrier drift process according to a preset step length; based on the Sockley-Ramo theorem, calculating the quantity of electric charges induced on the electrode during electron and hole drift step by step; repeatedly calculating a preset number of simulation cases to generate a nuclide characteristic energy spectrum database; carrying out normalization processing after the simulation energy spectrum and the actually measured background energy spectrum are superposed, and optimizing mobility life product parameters through a least square method; and regenerating a complete database containing single nuclides and mixed nuclides by adopting the optimized parameters for machine learning training.

Fission reactions within a molten salt reactor may produce gaseous fission products. These fission products may be removed through a variety of methods. However, proper removal of such fission products requires a thorough understanding of the proportion of gaseous space to fluid space within the component being interrogated, known as the void fraction. The present invention provides a means for determining the void fraction within such a component utilizing an enrich cadmium zinc telluride detector to produce collimated radiation data. The collimated radiation data may then be used to compute a mean void fraction across the domain being interrogated.

The application discloses a kind of orthogonal strip CZT detector module and method for particle therapy range and dose monitoring, orthogonal strip CZT detector module includes orthogonal strip CZT detector, signal front-end electronics circuit, channel compression circuit;Anode electrode and cathode electrode in orthogonal strip CZT detector are long strip and mutually orthogonal setting;Channel compression circuit reduces the channel number of signal output.According to user demand, the present application can realize the switching of single probe measurement mode and coincidence measurement mode, the method for monitoring the secondary particle intensity generated by the interaction of primary beam particles and human tissue in particle beam therapy field, the position and dose of particle primary beam irradiation target body or human body are calculated by secondary particle counting rule, so as to realize the monitoring of particle beam range and dose, the present application reduces the channel number of readout electronics and reduces the complexity of data acquisition, modular design meets the characteristics of economy and miniaturization.

This invention discloses a PN junction-type CZT detector with one ohmic and one Schottky contact and its fabrication method, relating to the field of semiconductor technology. The detector includes a detector body, a cathode, and an anode. The upper surface of the detector body serves as the anode, which is an Au / In composite electrode. The lower surface of the detector body serves as the cathode, which is an Au / Cr composite electrode. In this invention, the detector uses a Schottky contact on one side and an ohmic contact on the other. The anode acts as a collecting electrode, forming a Schottky contact that creates a downwardly bent potential barrier to resist hole injection and reduce leakage current. The cathode acts as a voltage-applying electrode, forming an ohmic contact. In this structure, a negative voltage is applied to the cathode. Ideally, the bias voltage is applied directly to the p-n junction, i.e., the Schottky contact, through the ohmic junction. As the potential barrier gradually decreases, the voltage is gradually applied to the bulk resistance, which begins to deplete downwards from the junction until it is completely depleted.

The invention relates to the technical field of radioactivity detection instruments, and discloses a radiation detection data processing method which comprises the following steps: step 1, acquiring detection data of a CZT detector, and boosting and amplifying the detection data to form a gain signal source; 2, processing the gain signal source by adopting a first preset filtering algorithm, extracting a pulse signal amplitude value, setting a comparison threshold value, comparing the pulse signal amplitude value with the comparison threshold value, and when the pulse signal amplitude value is greater than the comparison threshold value, adding 1 to pulse counting to obtain a pulse counting result; when the amplitude value of the pulse signal is smaller than a comparison threshold value, rejecting; and step 3, converting the pulse counting result to obtain a radiation dose value, and processing the radiation dose value by adopting a second preset filtering algorithm. The method can improve the stability and accuracy of the detection result. Meanwhile, the invention further provides a radiation detection device.

The real-time detection system comprises a coal transmission device based on communication connection, an X-ray light source, a CZT type detector, a DCS data processing module, a coal quality database module, an online calculation module and a real-time display module. The on-line calculation module stores a neural network-based coal quality component calculation program and a parameter library, coal quality is processed and analyzed by using DCS data, detection data and coal quality database information, real-time calculation and classified prediction of coal quality components are realized, and the real-time display module displays coal quality component data in real time. According to the invention, the flow and component information of the coal entering the furnace can be obtained and calculated on line, and can be displayed in real time in an imaging manner.

The invention discloses an orthogonal strip-shaped CZT detector module and method for particle therapy range and dose monitoring. The orthogonal strip-shaped CZT detector module comprises an orthogonal strip-shaped CZT detector, a signal front-end electronics circuit and a channel compression circuit. An anode electrode and a cathode electrode in the orthogonal strip-shaped CZT detector are strip-shaped and are arranged in an orthogonal manner; the channel compression circuit reduces the number of channels for signal output. According to user requirements, switching between a single-probe measurement mode and a coincidence measurement mode can be achieved, and the position and dosage of a target body or a human body irradiated by a particle main beam are calculated according to a secondary particle counting rule by monitoring the intensity of secondary particles generated by interaction of the main beam particles and human tissue in a particle beam treatment site. According to the invention, the number of readout electronics channels is reduced, the complexity of data acquisition is reduced, and the modular design meets the requirements of economical efficiency and miniaturization.