895 results about "Radioactive source" patented technology

The invention belongs to but is not limited to the technical field of three-dimensional space dose visualization, and discloses a three-dimensional nuclear emergency radiation field calculation and visualization method and system, based on a point nuclear method, a cumulative factor, mass attenuation factor and flux rate-dose rate conversion factor database is established, a mean free path solving algorithm is optimized, and a three-dimensional nuclear emergency radiation field is obtained. The geometric types of radioactive sources are expanded, and the dose calculation efficiency is improved through parallel calculation; plane dose rate drawing at a certain height is realized based on a two-dimensional texture mapping method; three-dimensional space dose rate contour surface drawing is realized based on a moving cube algorithm; and three-dimensional space dose rate volume rendering is realized based on a three-dimensional texture volume rendering technology. Radiation field dose calculation, three-dimensional radiation field dose visualization and GIS are integrated, and the system is used as a subsystem of a nuclear emergency aid decision simulation platform. The dose distribution diagram in the area can be judged more visually, and the method has a good help effect on nuclear emergency command.

The invention discloses an adaptive energy calibration method for a Timepix3 detector, and belongs to the field of plasma diagnosis, and the method comprises the steps: collecting a photon event through a detector, the photon event comprising arrival time, coordinates and energy information; sorting the photon events according to the arrival time of the photon events to obtain a sequence; mapping the sequence to an empty matrix in a time window sliding mode, searching and recording the area of a pixel cluster and the sum of count values, and compensating the count values according to a set threshold value; classifying according to the area of the pixel cluster, summing the counting values of the pixels in the pixel cluster to obtain the volume of the pixel cluster, and drawing a statistical histogram of the volume of the pixel cluster to form an energy spectrum; identifying an energy peak of each energy spectrum and performing Gaussian fitting, calculating a peak abscissa, and establishing a relationship between the volume of a pixel cluster and actual energy; and completing energy calibration by utilizing linear fitting of volume energy data of multiple groups of pixel clusters. According to the invention, the requirements for setting parameters such as radioactive source intensity, detector threshold, exposure time and the like are reduced.

The invention relates to the field of nuclear radiation detection, and provides a Compton camera image reconstruction method and electronic equipment, and the method comprises the steps: collecting multiple event data generated by a target radioactive source in multiple events; for each event in the multiple events, reconstructing the back-projection cone based on a back-projection algorithm according to the event data of the event to obtain coordinate representation of the spatial position of the back-projection cone; determining an initial coordinate of the target radioactive source according to the coordinate representation of the plurality of back projection cones of the multiple events in the plane where the target radioactive source is located; for each event in the multiple events, determining the weight of the event based on the initial coordinate of the target radioactive source and the event data of the event; and utilizing a model based on a maximum likelihood expectation maximum algorithm to perform iterative reconstruction based on the weight of multiple events to obtain a reconstructed image. By means of the method, the spatial resolution and reconstruction efficiency of the image formed by the Compton camera system can be improved.

The invention discloses a fast neutron energy spectrum unfolding method based on an artificial neural network, which is used for reversely solving a neutron energy spectrum of a neutron field according to a neutron recoil proton spectrum recorded by a liquid scintillator detector. The neural network model is developed based on a generative adversarial neural network and comprises a generator and a discriminator. According to the neural network, Geant4 is used for simulating neutron energy response of an EJ301 liquid scintillator detector, and a data set containing 20000 samples is constructed for training of the neural network. The provided neural network spectrum unfolding algorithm is verified by using neutron energy spectrums of 252Cf and 241Am-Be radioactive sources. The neural network model can generate accurate neutron energy spectrum data under 6 keV energy resolution, and the Qs quality factor evaluation proves that the generated neutron energy spectrum is basically consistent with the target energy spectrum.

The invention discloses a Ga2O3 heterojunction beta irradiation battery with a multi-groove radioactive source, relates to the technical field of microelectronics, and solves the problems of low energy utilization rate and low energy conversion efficiency of a Ga2O3 nuclear battery radioactive source in the prior art. The battery comprises a filling type multi-groove radioactive source; the Ga2O3 heterojunction diode unit sequentially comprises a P-type ohmic contact electrode, a P-type NiO ion implantation region, an N-type Ga2O3 low-doped epitaxial layer, an N-type Ga2O3 high-doped substrate and an N-type ohmic contact electrode from top to bottom; a multi-T-type radioactive isotope source layer in the filling type multi-groove radioactive source is arranged above the P-type NiO ion implantation region and forms radiation energy coupling with the Ga2O3 heterojunction diode unit; the groove type structure is filled with the radioactive source, the energy deposition of the radioactive source entering the semiconductor conversion device is greatly increased, and the energy conversion efficiency of the Ga2O3 beta irradiation battery is improved.

The invention relates to the related technical field of primary cell (PDC) culture, in particular to a method for culturing primary cells (PDC) from glioma patients, which comprises a series of steps of Swis3T3-J2 cell culture, conditioned medium preparation, brain tumor tissue pretreatment, primary tumor cell digestion and culture and the like. Primary human tumor cells are cultured by a conditioned culture medium generated by fibroblasts irradiated by X-rays (X) and a cobalt-60 radioactive source (60Co), and culture conditions of key features of parent tumors and a modeling process can be most effectively reserved by screening and optimizing the culture conditions. And whether the PDC retains the key characteristics of the parent tumor or not is inspected on the aspects of the cell molecular level, the cell phenotype, the animal intracranial tumor model and the like.

The invention discloses a dynamic calculation method and system for a radiation field in the cutting process of an activity non-uniform radioactive source, and belongs to the field of radiation field calculation. The method comprises the following steps: acquiring three-dimensional activity distribution data of a radioactive source; constructing a voxelization model and coupling the voxelization model with an activity grid to distribute activity; establishing an LBVH hierarchical structure of the shielding body; a point kernel is generated in a self-adaptive mode through ray tracing and average free path comparison; carrying out radiation field calculation by adopting point nuclear integration, and realizing multilayer ray tracing in the radioactive source, between the sources and a shield in the process; on-line cutting and moving operation of the voxel model is supported, and the radiation field is dynamically updated. According to the method, the cutting operation of the activity non-uniform radioactive source can be simulated, the problem that the radioactive activity of each cutting product cannot be represented after cutting by a traditional method is solved, the radiation field dynamic calculation in the activity non-uniform radioactive source cutting process can be simulated, initial modeling of the radiation environment only needs to be carried out once, and the efficiency is improved. And repeated modeling is not needed.

The invention provides an X-ray photovoltaic radiation cell based on a gallium-containing semiconductor and a preparation method of the X-ray photovoltaic radiation cell. The gallium-containing semiconductor X-ray radiation photovoltaic cell comprises a gallium-containing semiconductor transduction unit and an X-ray radiation source 55Fe arranged on the semiconductor transduction unit, wherein the semiconductor transduction unit containing gallium comprises at least one of GaAs (gallium arsenide), GaInP (gallium indium phosphide), GaP (gallium phosphide) and Ga2O3 (gallium trioxide). According to the invention, the structure of a radiation photovoltaic cell is adopted, the output power density of an X-ray radioactive source 55Fe can be effectively improved, the penetration depth of the X-ray source 55Fe in a semiconductor can be effectively shortened by taking GaAs, GaInP, GaP and Ga2O3 as semiconductor materials, and meanwhile, the collection capability of current carriers is effectively improved by adjusting the total thickness of a semiconductor transduction unit and the doping concentration of each layer, so that the performance of the X-ray source 55Fe is improved. And finally, the preparation of the X-ray radiation photovoltaic cell with high output power and high energy conversion efficiency is realized.

The invention relates to an automatic calibration device and method for continuously monitoring smoke dust concentration, and belongs to the technical field of environment monitoring. The device comprises a drying device, a dynamic heating system, a receiver and a radioactive source, a drying position, a sampling position and a detection position are sequentially arranged from left to right or from right to left; wherein the position where the drying device is located is a drying position, the lower portion of an exhaust pipe wrapped by the dynamic heating system is a sampling position, and the middle position where the receiver and the radioactive source are located is a beta-ray intensity detection position; and calculating the concentration of the smoke dust to be measured by adopting a smoke dust concentration automatic calibration algorithm according to the measured beta-ray intensity and sampling flow. According to the invention, long-time, high-precision, continuous and reliable operation of the light scattering smoke dust concentration continuous monitoring instrument can be ensured.

The invention relates to hot rolled plate thickness measuring equipment, and belongs to the technical field of detection equipment. The hot-rolled plate thickness measuring equipment comprises a control module and a plurality of detection mechanisms. Each detection mechanism comprises a radioactive source and a detection assembly. The detection assembly and the radioactive source are oppositely arranged in the thickness direction of the hot-rolled plate, and a gap for the hot-rolled plate to penetrate through is reserved between the detection assembly and the radioactive source. The detection mechanism is used for measuring the actual thickness size of the hot-rolled plate at the position; at least part of the multiple detection mechanisms can move in a reciprocating mode in the width direction of the hot rolled plate. And the control module controls the detection mechanism to stop or move in the width direction of the hot-rolled plate based on the variance of n actual thickness sizes of the hot-rolled plate continuously measured by the detection mechanism at the same position. The hot-rolled plate thickness measuring equipment provided by the invention can accurately measure the thickness dimension data of each part of the hot-rolled plate.

The invention relates to the technical field of medical imaging, and discloses an image reconstruction method and device for a Compton camera, computer equipment and a storage medium. Comprising the following steps: acquiring current weight distribution and reference weight distribution corresponding to an imaging plane; real radioactive source simulation is carried out based on the current weight distribution, and simulation weight distribution corresponding to the imaging plane is obtained; updating elements in the current source set according to the simulation weight distribution and the reference weight distribution to obtain an updated source set so as to perform image reconstruction on the Compton camera; wherein elements in the current source set are used for representing radioactive source coordinates corresponding to Compton events occurring in the Compton camera. Therefore, the image reconstruction method capable of improving the imaging quality of the Compton camera is realized, and the reconstructed image can reflect the actual distribution condition of the radioactive source more accurately, so that a reliable basis is provided for real-time monitoring of the boron concentration in the BNCT treatment process.

The invention discloses a visual classification and intelligent analysis integrated radioactive source automatic verification system and method. The system is characterized by comprising a master control system, a grabbing device for automatically clamping and carrying a source box, automatic verification equipment for automatically verifying the source box, a carrying device for automatically conveying and storing the verified source box, and a lifting platform for driving the source box to lift. The mechanical arm drives the carrying device to replace manual work to clamp the source box on a truck to the automatic verification equipment, the automatic verification equipment automatically verifies the source box, after verification is completed, the mechanical arm drives the carrying device to clamp the source box to the material frame, and the carrying device carries and stores the source box on the material frame to the corresponding stock bin. And automatic verification and storage are realized, so that the identification accuracy and the storage operation efficiency of the radioactive source are improved, and the radiation risk and the labor intensity of personnel are reduced.

The invention discloses a method for determining the width value of an avalanche air gap of a gas detector and a related device, and belongs to the technical field of detectors. The method comprises the following steps: sequentially obtaining a plurality of energy spectrum groups of an anode reading plate under a plurality of different voltages when the anode reading plate is irradiated by a radioactive source; obtaining an original electron number; for the energy spectrum group corresponding to each voltage, obtaining the detector gain corresponding to the voltage based on the energy spectrum group and the primary electron number; determining a gas parameter and a photon feedback item corresponding to the voltage; determining a width value of an avalanche air gap under the voltage based on a detector gain corresponding to the voltage, a gas parameter corresponding to the voltage and a photon feedback item corresponding to the voltage; and determining the final width value of the avalanche air gap of the gas detector based on the width values of the avalanche air gaps under the plurality of different voltages. According to the invention, the accuracy of the determined width value of the avalanche air gap can be improved, so that the avalanche air gap of the gas detector is accurately calibrated.

The invention provides a scattering artifact image correction method and device, equipment and a storage medium, which can be applied to the technical field of medical images. The method comprises the steps that a projection signal related to a target detection object is obtained, the projection signal is obtained by scanning the target detection object based on m projection angles through a radioactive source, and m is an integer larger than 1; determining a target sampling angle from the m projection angles by using a gradient sampling algorithm; obtaining a sparse scattering signal corresponding to the target sampling angle, the barrier plate being arranged between the radioactive source and the target detection object; processing the sparse scattering signals corresponding to the target sampling angles based on an interpolation algorithm to obtain target scattering signals corresponding to the m projection angles; and performing image reconstruction according to the projection signals corresponding to the m projection angles and the target scattering signal, and generating a scattering artifact correction image.

The invention discloses a rapid large-scale calculation simulation method and system for gamma radiation dose in a dynamic environment and a storage medium, and belongs to the technical field of ionizing radiation protection. The method comprises the following steps: firstly, constructing a triangular mesh scene model containing a radioactive source and a shielding body, and discretizing the radioactive source into a local point kernel; global coordinates of the point kernel and the vertex of the triangle are calculated in parallel by using a GPU, and a maximum parallelization hierarchical surrounding structure MPBVH of the scene is constructed; ray tracing is executed in parallel on the GPU, and all intersection points of MPBVH calculation rays and the shielding body are traversed to determine the thickness and the material of each shielding layer; and finally, dose values of all counting grids are calculated in parallel by adopting a point kernel method. When a radioactive source or a shielding body in a scene is subjected to dynamic changes such as movement and rotation, geometric data can be quickly updated, and calculation can be executed again. According to the method, the speed of large-scale point kernel calculation is increased, the influence of the environmental complexity on large-scale calculation time consumption is small, and the method can be suitable for rapid large-scale calculation and dynamic updating of the radiation field in the complex dynamic environment.

The invention relates to a radioactive source library management system, which comprises an intrusion detection unit comprising an infrared detector, an infrared camera and an emergency alarm device; a video monitoring unit; the radiation value detection unit comprises a fixed point radiation detector and a tracing robot moving radiation detector; an access control unit; the management and control platform unit is respectively connected with the intrusion detection unit, the video monitoring unit, the radiation value detection unit and the access control unit and is used for carrying out data acquisition on each unit, and the management and control platform unit is connected with the dynamic display unit and is used for providing display and alarm information for the dynamic display unit. Moving a radiation detector through a tracing robot to regularly collect the radiation dose in the radioactive source library, and judging whether the real-time number of the radioactive sources in the source library and the radiation dose are safe or not; manual collection is not needed, a radiation monitor does not need to be arranged for each radioactive source, the number of devices is reduced, meanwhile, the radiation detector does not need to be fixed to a radioactive source tank, touch is avoided, and damage is not prone to occurring.

The embodiment of the invention discloses a double-nuclide PET reconstruction method and device based on a joint Poisson model, and the method comprises the steps: coincidence data collection and random three-coincidence estimation: retaining the photon correlation in decay through a coincidence delay window, and estimating the random three-coincidence through the photon irrelevance between decay; establishing a combined Poisson distribution model, introducing impure electron nuclides, pure electron nuclides and random radioactive source distribution into the distribution model at the same time, and constructing a combined Poisson likelihood function; constructing a prior function according to the image features, and forming a target function with the combined Poisson likelihood function; and solving the maximum posteriori estimation of the target function to obtain the spatial distribution of non-pure electron nuclides, pure electron nuclides and random radioactive sources at the same time. The dual-nuclide PET imaging method can be directly applied to the dual-nuclide PET imaging field based on triple coincidence, and has the advantages of being capable of effectively inhibiting random triple coincidence artifacts and the like.

The invention relates to a shielding transportation device for an Sr-90 radioactive source, which comprises a shielding container, a protective cover and a transportation bracket, the protective cover is arranged at the upper part of the shielding container, and the transportation bracket is arranged at the lower part of the shielding container; the shielding container comprises a shielding container cylinder, the shielding container cylinder comprises an outer container and an inner container, the inner container is arranged in the outer container, a spring is arranged below the inner container, and the inner container is used for loading an Sr-90 radioactive source. Compared with the prior art, the device can meet the requirement that the radioactive source is loaded and unloaded in a horizontal state, can prevent the radioactive source from scattering under the condition of a transportation accident, still has enough shielding capability, has good transportation interface performance, and can ensure the safety in the transportation process. The chemical forms of the transported Sr-90 comprise 90SrO, 90Sr (NO3) 2 and 90SrTiO3, and the item forms of the transported Sr-90 cover powder, ceramics, solutions, pellets and the like.

The invention relates to the technical field of gamma radiation dose calculation, and particularly discloses a gamma radiation dose calculation method based on a Unity engine, a program, equipment and a storage medium. In order to solve the problems that ray tracing is complex and low in efficiency in complex irregular geometry by means of an existing point kernel integration method, the physical calculation capacity of a Unity engine is introduced, ray tracing is conducted through Physics. Raycast interface iteration, and gamma radiation dose calculation under the multi-layer shielding condition is optimized. The method comprises the following steps: acquiring radioactive source energy, intensity, shielding body density, mass attenuation coefficient and detection point coordinates; constructing a radioactive source model and generating a point kernel set through parallel array ray discretization; performing ray tracing on the point core set to obtain a list of all intersection points of rays and the shielding body; and calculating the shielding thickness of each layer according to the intersection point list, calculating the dose contribution of each point core in combination with the accumulation factor, and summing to obtain a total dose value.

A radiation safety apparatus for a semiconductor processing system has a safety fence with a support frame and radiation shields defining containment regions associated with load ports of the semiconductor processing system. The containment regions are associated with radioactive sources that emit radioactive radiation, where radiation shields attenuate the radiation to a region external to the containment regions. The radiation shields have access doors movably coupled to the support frame to provide access to the containment regions. Interlocks are provided with the access doors to selectively lock the access doors in a closed position to control the access to the containment regions from the external region through the access doors. A controller controls the interlocks based on a radiation decay associated with each of the radioactive sources and a predetermined safe radiation exposure level.

The invention discloses a low-source component positron annihilation lifetime spectrometer for micron-sized film measurement, and relates to the field of positron annihilation lifetime. In the spectrometer, a positron annihilation lifetime measuring device is used for detecting gamma photons generated by decay of a radioactive source as initial detector signals; detecting gamma photons generated by annihilation of positron in the film sample as termination detector signals; the anticoincidence device is used for detecting anticoincidence signals generated when positron does not annihilate in the film sample; the positron annihilation life measuring device performs time coincidence judgment on a starting detector signal and a terminating detector signal of a case that positron annihilation occurs in a film sample according to the anti-coincidence signal, calculates a time difference between the starting detector signal and the terminating detector signal meeting a time condition, and counts the time difference. And drawing a positron annihilation lifetime spectrum. According to the invention, the source components in the positron annihilation lifetime spectrum are greatly reduced, and the measurement of the film sample by using a simple device is realized.

The invention discloses a real-time determination method, system and equipment for residence time of an afterloading radioactive source, and relates to the technical field of radioactive source detection, and the method comprises the steps: obtaining a radioactive source contour from a video image, screening a longest transverse line segment from the video image, and obtaining an end point coordinate of the longest transverse line segment; searching each scale point on the scale line from the end point coordinate along the direction perpendicular to the scale line by utilizing an iterative vertical line scale line method, selecting the scale point corresponding to the minimum distance from all the distances according to the distance between each scale point and the end point coordinate, and taking the scale point as a radioactive source coordinate; recording the radioactive source coordinate of each frame in the video image, eliminating and fusing the noise frame, obtaining the staying duration of the radioactive source in each radioactive source coordinate according to the video frame rate of the video image and the radioactive source coordinate of each frame, and filtering the preset short staying duration from all the staying durations. According to the invention, the residence position and time of the afterloading radioactive source can be accurately determined.

The invention relates to a radiation contamination simulation detection equipment control method based on an ultraviolet fluorescence signal, which is applied to radiation contamination simulation detection equipment, and the equipment comprises a detection probe. The method comprises the steps that a fluorescence intensity original signal and an ambient light interference signal of a target area are collected, the distance between a detection probe and a target surface is obtained, a fluorescence simulation agent is sprayed on the target area and irradiated by an ultraviolet LED lamp, and the simulation agent is used for emitting fluorescence with the wavelength larger than 450 nm under excitation of ultraviolet light; based on the distance and the ambient light interference signal, performing coupling compensation on the fluorescence intensity original signal; and calculating a radiation simulation value according to the calibration fluorescence intensity signal, and outputting information such as the radiation simulation value, the safety level and the component type. According to the method, through non-radiation simulation agent replacement, signal calibration and multi-dimensional analysis technical means, the safety of radiation detection training is improved, the health threat of a real radioactive source to trainees is eliminated, and the accuracy and the information amount of a detection result are remarkably improved.

The invention provides a radioactive biological experimental facility radiation environment monitoring and personal dose monitoring method, which comprises a fixed radiation dose monitor, a portable radiation dose monitor, a personal dose instrument, an experimental facility computer system docking port, an analysis center and an early warning judgment module, the experimental facility environment radiation dose can be monitored in real time, single-time operation personal cumulative doses under three different conditions can be obtained through an experimental facility computer system, radiation dose summary analysis can be carried out on radioactive sources operated in the experimental facility, radiation dose changes under different radioactive source operations are obtained, and the experimental facility environment radiation dose monitoring system can be used for monitoring the experimental facility environment radiation dose in real time. And finally, performing early warning according to the environmental radiation dose and the individual accumulated dose result. The environment radiation state can be monitored timely, accurately and effectively, and the external irradiation dose of personnel can be monitored and evaluated in real time.

The invention relates to a double-cavity radiotherapy and chemotherapy integrated treatment capsule for brain glioma, which aims to solve the problems that the existing radioactive seed source or chemotherapy carrier cannot give consideration to radiotherapy and chemotherapy, the dosage is difficult to regulate and control, the medicine distribution is non-uniform and the like. The brain glioma double-cavity radiotherapy and chemotherapy integrated treatment bag is composed of a radiotherapy pipeline and a chemotherapy pipeline, the whole integrated treatment bag is a spiral pipe body, the radiotherapy pipeline is located in an inner ring, the chemotherapy pipeline is located in an outer ring, the radiotherapy pipeline is a closed cavity, a liquid radioactive source is contained in the closed cavity, and the liquid radioactive source is located in an outer ring. The chemotherapy medicine is released from the head end of the chemotherapy pipeline, the chemotherapy medicine is injected from the tail end of the chemotherapy pipeline, and the surface of the integrated treatment bag is coated with a composite antibacterial layer. According to the integrated treatment capsule, radiopharmaceuticals and chemical drugs are placed in the inner cavity and the outer cavity respectively, synergistic treatment of radiotherapy and chemotherapy is achieved through the synchronous effect of the two channels, and long-term low-dose release of the radiopharmaceuticals and the chemotherapy drugs is achieved and toxic and side effects are reduced by adjusting the screw pitch and the thickness of the tube wall.

The invention provides a radioactive source personal dose real-time monitoring device and a radioactive source personal dose real-time monitoring method based on a double-range self-adaptive mechanism. The radioactive source personal dose real-time monitoring device and method are suitable for intraoperative individual dose collection and dynamic evaluation in the tumor radiotherapy process. The device comprises a flexible attaching substrate, a first measuring range detection sub-module, a second measuring range detection sub-module, a self-adaptive scheduling unit, a temperature compensation module, a breathing synchronous correction module and a wireless communication module. The device can respond to different dose intensities in real time and adaptively switch or fuse channels; the collected dose projection is restored to a planned coordinate system through a breathing phase recognition and target region drift model, and dynamic target region dose tracking is achieved; temperature correction and wireless transmission functions are combined, and intraoperative data visualization and postoperative evaluation are supported. According to the invention, the precision and safety of radiotherapy dose monitoring are improved, and the method is especially suitable for radiotherapy management of areas with significant respiration-induced drift or adjacent key organs.

The invention relates to a gamma radiation field simulation method, a gamma radiation monitoring simulation training system and application of the gamma radiation field simulation method and the gamma radiation monitoring simulation training system, and a three-dimensional simulation gamma radiation field and the gamma radiation monitoring simulation training system are constructed based on the Beidou positioning technology, the computer and communication technology and the action law of gamma rays and substances. The simulation training system is composed of a guide center, a Beidou positioning and communication base station, a simulation training ground, a simulation gamma radioactive source and a simulation gamma radiation monitor. The parts of the system exchange information through wired or wireless communication. The simulated gamma radiation source and the simulated gamma radiation monitor both have an accurate positioning function, and the simulated gamma radiation monitor also has a function of calculating and obtaining a gamma radiation dose rate and a dose. The problem of simulation and monitoring simulation training of a space gamma radiation field generated by a plurality of real gamma radioactive sources is solved, so that the effects of simulation training such as searching for more than one gamma radioactive source, determining gamma radioactive contamination boundaries and measuring personal accumulated doses are close to reality.

The invention discloses a collimation array detection system for measuring radioactive source distribution in a complex radiation field, and solves the problems that a traditional complex radiation field construction method is long in time consumption and low in efficiency, the resolution ratio of obtained radioactive source distribution information is low, and life health and safety of workers are difficult to guarantee. The device specifically comprises a detection unit, a collimation shielding unit and a data processing unit. The detection unit comprises a PCB (Printed Circuit Board) assembly, an N * N detector array and a buffer gasket, wherein N is greater than or equal to 2; the N * N detector array is installed on the PCB assembly. The buffer gasket is arranged on the detection end face of the N * N detector array; the collimation shielding unit comprises a detection shell and a collimation assembly which are connected with each other; the PCB assembly, the N * N detector array and the buffer gasket are all mounted in the detection shell; n * N collimation channels penetrating through the two ends of the collimation assembly are arranged in the collimation assembly; the data processing unit is connected with the N * N detector array through the PCB assembly.

Systems and methods are provided for treating cervical and / or uterine cancers in brachytherapy with an intracavitary brachytherapy applicator. The system comprises a tandem adapted for insertion into a cervix of a patient. An ovoid assembly comprises first and second inflatable ovoids and an ovoid support mechanism. The first and second inflatable ovoids are adapted for insertion within fornices of a patient. First and second retractors are adapted to be coupled to the ovoid assembly. The first retractor is adapted to be positioned to retract the bladder of a patient during treatment. The second retractor is adapted to be positioned to retract the rectum of a patient during treatment. The tandem and the first and second inflatable ovoids are adapted to be coupled to a radioactive source to deliver an implant radiation dose suitable for cancer treatment at a cancerous cervical treatment site in a patient.