163results about How to "Reduce radiation dose" patented technology

The invention discloses a virtual dynamic three-dimensional image fusion method and system based on pre-registration, and the method comprises the steps: obtaining a static three-dimensional image of a target region, and a dynamic three-dimensional CBCT image which at least comprises one respiratory cycle; performing breathing phase division on the dynamic three-dimensional CBCT image; obtaining a corresponding three-dimensional image frame on each phase node; registering the plurality of three-dimensional image frames obtained by division with the static three-dimensional image in sequence to obtain a single-frame deformation field; collecting breathing signals of a patient in real time during an operation; performing interpolation calculation on the single-frame deformation field based on the respiratory signal, and generating a complete deformation field in the whole respiratory cycle in real time; and applying the complete deformation field obtained by interpolation to the static three-dimensional image, so that the static three-dimensional image is virtually dynamic. Through a method of pre-registration of a pre-operative breathing phase node image and interpolation based on a real-time breathing phase in an operation, the calculation amount during real-time fusion in the operation is reduced, so that ultra-low-delay image fusion is realized.

The invention relates to the technical field of medical image processing, in particular to a nasopharyngeal carcinoma pseudo CT generation method based on multi-modal deformation registration and a Transform network, and the method comprises the steps: firstly collecting CT and MRI images of a nasopharyngeal carcinoma patient confirmed by pathology, and carrying out the preprocessing of the CT and MRI images; secondly, establishing a deformation registration network based on a CycleFCNs model, inputting the CT image as a fixed image and the MRI image as a floating image, outputting a space deformation transformation field, and performing deformation transformation on the MRI image; then, a decoder is added on the basis of the original Transform model, a loss function is set, and the weight is adjusted; the image subjected to deformation registration is used as training data to be input into the improved Transform model for training optimization; and finally, generating a pseudo-CT image from the to-be-processed MRI image by using the trained model, and performing imagery evaluation by using various evaluation indexes. The accuracy and quality of pseudo CT generation are improved, the radiation dose of a patient is reduced, and the method has important clinical application value in the field of nasopharyngeal carcinoma radiotherapy.

The present invention relates to the field of molecular imaging, nuclear medicine and single-domain antibody technology for tumor diagnosis and treatment, and in particular to a method for preparing a radionuclide-labeled Trop2-specific single-domain antibody probe and its application. The Trop2-specific single-domain antibody has a CDR1 having an amino acid sequence shown in SEQ ID No.1, a CDR2 having an amino acid sequence shown in SEQ ID No.2, and a CDR3 having an amino acid sequence shown in SEQ ID No.3. The Trop2-specific single-domain antibody prepared by the present invention 18 The F-labeled single-domain antibody probe is used for immuno-PET imaging, which realizes the non-invasive visualization of Trop2 in vivo and further realizes the non-invasive diagnosis of Trop2-positive tumors. The probe has the advantages of simple preparation process, low cost, high specificity, high stability, short imaging cycle, low radiation dose, and easy clinical transformation.

The utility model relates to the technical field of radiation protection, and discloses an X-ray photography full-isolation radiation protection device, which comprises an X-ray photography full-isolation radiation protection device, a central beam limiting system, a beam limiting device position signal communication port, a detector height signal communication port, a peripheral shielding interlayer and an examination room. According to the X-ray photography full-isolation radiation protection device, automatic switching of the protection position and the protection state is completed in time, the shooting efficiency is not affected, and the staying and positioning time of a subject is not increased. The X-ray radiography full-isolation radiation protection device can provide a rapid, effective and accurate X-ray protection effect for DR equipment shooting, and examinees, accompanying family members and technicians do not need to wear protection equipment such as lead clothes, so that the probability that non-examined parts, especially gonads and the like, are exposed to direct X-ray irradiation and scattered ray irradiation is greatly reduced, and the X-ray radiography full-isolation radiation protection device is suitable for being used in X-ray radiography. Furthermore, effective guarantee is provided for the health of examinees and technicians, and important social benefits and popularization value are achieved.

The invention discloses a harmless treatment method for rare earth smelting waste residues, and relates to the technical field of hazardous waste treatment and disposal. The method comprises the following steps: firstly, adding an organic barium salt into the rare earth smelting waste residue, stirring to react completely, then adding a carbonate mineralizing bacteria culture solution to carry out induced mineralization reaction, after the reaction is completed, pressurizing and compacting the rare earth smelting waste residue, carrying out carbonization maintenance, and drying after the maintenance is completed, so that the harmless treatment of the rare earth smelting waste residue is realized. The method for harmlessly treating the rare earth smelting waste residues has the advantages that the method is green and environment-friendly, the radioactivity of the rare earth smelting waste residues can be reduced in situ, the cementing effect on the rare earth smelting waste residues is good, and subsequent secondary utilization is not affected.

The invention discloses an orthogonal DR-based adaptive planning method and related equipment, and relates to the technical field of radiotherapy, and the method comprises the steps: carrying out the automatic segmentation of a planned CT image of a patient, and obtaining a segmentation result; the segmentation result comprises a target region of the patient or a delineation set of an organ at risk; after a patient is positioned, DR images of the patient in two orthogonal directions are collected; projecting the planned CT image of the patient in the space of the positioning coordinate system to obtain a corresponding orthogonal DRR image; performing registration on the DR images in the two orthogonal directions and the corresponding DRR images to obtain 2D deformation grids in the two orthogonal directions; reconstructing a 3D deformation field through the 2D deformation grid; acting the 3D deformation field on the sketching set to obtain a deformation component of the corresponding target area or the endangered organ of the patient; determining whether to recollect the CT image of the patient according to the deformation component; the CT scanning frequency can be reduced, and meanwhile real-time evaluation of tumor changes is achieved.

The invention relates to the technical field of medical information management, and particularly discloses a stomach cancer postoperative MRD dynamic monitoring system based on multi-biomarker fusion, which is used for solving the problem that in the prior art, CT and MRI equipment cannot dynamically adjust parameters according to real-time recurrence risk of a stomach cancer postoperative patient, so that the stomach cancer postoperative MRD dynamic monitoring system is poor in reliability. The system comprises a biomarker data acquisition module and a recurrence risk analysis module, and further comprises a CT equipment parameter adjustment module, an MR I equipment parameter adjustment module, a feedback control module and an examination means optimization module. Through fusion of multiple biomarkers, dynamic monitoring of gastric cancer postoperative MRD is realized, CT and MRI parameters are adaptively adjusted based on the recurrence risk of a patient, imaging precision is improved, equipment operation is optimized, radiation and imaging time are reduced, and precise CT and MRI imaging equipment parameter management is realized.

The invention belongs to the field of coaxial cables, and particularly relates to a cross-linked foaming polyethylene core wire coaxial cable. The cross-linked foaming polyethylene core wire coaxial cable comprises an inner conductor, an insulating layer, an outer conductor layer and an outer sheath layer which are sequentially coated from inside to outside, the insulating layer is prepared by the following method: S1: performing foaming extrusion on a base material, a cross-linking agent and a nucleating agent to obtain an insulating core wire; during foaming extrusion, foaming gas is adopted for physical foaming; the base material is selected from high-density polyethylene; and S2, performing irradiation crosslinking on the insulating core wire through high-energy rays (such as gamma rays, alpha rays and electron rays) to obtain an insulating layer. The cross-linked foaming polyethylene core wire coaxial cable is suitable for high-temperature-resistant occasions including high-power high-frequency signal transmission occasions and coaxial cable frequent welding occasions, and can meet the requirements of a high-end communication system.

The invention provides a multifunctional guide column grabbing tool. The multifunctional guide column grabbing tool comprises a hanging ring, an operation handle, a hook claw operation handle, a rod body, an inner sleeve, a mandrel and hook claws. The hanging ring is installed on the top of the rod body. The operating handle is located at the upper end of the rod body and used for an operator to adjust the posture of the multifunctional guide column grabbing tool through the operating handle. The lower end positioning pin of the rod body is inserted into the upper end round hole of the long guide column rod body. The inner sleeve is located in the rod body and configured to slide up and down in the rod body. The lower end of the inner sleeve is provided with a boss structure, and the upper end of the inner sleeve is provided with a claw operating handle. The mandrel is located in the inner sleeve, the upper end of the mandrel is matched with the manual torque wrench, and the lower end of the mandrel is matched with the long guide column locking rod. By integrating multiple functions of grabbing, transferring and screwing of the quick-release guide column, the technical problems that the operation time of operators is too long and the irradiation dose of field operators is increased due to the fact that the operation of the guide column is complex in the prior art are solved.

The invention belongs to the technical field of nuclear power station large flange face in-situ machining and repairing, and aims to solve the technical problems that in-situ machining and repairing on-site installation and adjustment of a nuclear power station large flange face need many workers, and efficiency is low. The invention discloses a rapid installation and adjustment device and method for nuclear power large flange face in-situ machining and repairing equipment, the device comprises a base device and an electric rapid expansion mechanism, the electric rapid expansion mechanism comprises a jacking screw rod, a jacking block and a transmission screw rod, the transmission screw rod is connected with a motor, and the motor drives the jacking screw rod to stretch out or retract; according to the method, an electric rapid expansion mechanism is installed on the side edge of a base device, rapid stretching or retracting of a jacking block is achieved through a driving motor, and rapid installation and adjustment of the nuclear power large flange face in-situ machining and repairing equipment are achieved. Rapid installation and adjustment of the nuclear power large flange face in-situ machining and repairing robot can be achieved, the on-site installation and adjustment time of personnel is shortened, and the radiation dose of the personnel is reduced.

The invention discloses a clamping jaw disassembly maintenance device for a refueling machine. The clamping jaw disassembly maintenance device comprises a main frame body mechanism, a lifting mechanism, an overturning clamping mechanism and a bearing mechanism. According to the disassembly and maintenance device for the clamping jaw of the refueling machine, the overturning clamping mechanism is arranged to clamp the clamping jaw of the refueling machine, and the lifting mechanism is arranged to drive the overturning clamping mechanism and the clamping jaw of the refueling machine to ascend and descend, so that the clamping jaw of the refueling machine can be conveniently disassembled by a maintainer in the vertical direction; and the clamping jaw of the refueling machine is overturned through the overturning clamping mechanism, so that the clamping jaw of the refueling machine can be conveniently transferred to the bearing mechanism, and the clamping jaw of the refueling machine can be conveniently disassembled by a maintainer in the horizontal direction. According to the disassembly and maintenance device for the clamping jaw of the refueling machine, lifting and overturning of the clamping jaw of the refueling machine can be easily achieved, the convenience of disassembling related parts of the clamping jaw of the refueling machine is improved, the working intensity of maintainers is greatly relieved, and the irradiation dose of the maintainers is further reduced.

The utility model discloses a pharmaceutical mixer, which comprises a base, a vertical plate, a rotating mechanism, a swinging mechanism and a fixing mechanism, and can ensure that a medicine bottle is stably and effectively clamped and fixed and then is quickly and uniformly mixed, thereby liberating both hands of a pharmaceutical worker, improving the working efficiency, greatly reducing the radiation dose suffered by the pharmaceutical worker, and ensuring the safety of the pharmaceutical worker. Through simple, convenient and efficient mechanical operation, the mixing uniformity of the medicine is greatly ensured, and the material control of the medicine is ensured.

The invention provides a teleoperation radiation-resistant metal mechanical property test sample preparation system, and belongs to the technical field of nuclear industry science, the teleoperation radiation-resistant metal mechanical property test sample preparation system comprises a cutting machine body for preparing and processing all radioactive metal samples, and the preparation system further comprises a purification system installed on the right side of the cutting machine body; the shielding system is mounted on the cutting machine body and the purification system; the cooling system is mounted on the rear side of the purification system; the automatic threading device is mounted on the cutting machine body and is used for providing uninterrupted copper wires for the sample preparation process; and the remote control system is installed at the far end and used for driving the cutting machine body, the purification system, the cooling system and the automatic wire penetrating device and monitoring the operation states of all the systems at the same time. According to the invention, the contradiction between irradiation sample preparation and harm of radioactivity to people and equipment is effectively solved, a radioactive source and an operator as well as the radioactive source and the sample preparation equipment can be isolated, and the operator and the sample preparation equipment are protected from being damaged by radiation.

The invention discloses a preparation method of modified phenolic resin for radioactive waste oil solidification, and relates to the technical field of nuclear radioactive waste treatment.The preparation method comprises the steps that phenolic resin obtained through base catalysis is modified; preparing a lead-based metal organic framework; adding the prepared lead-based metal organic framework into dimethylformamide to obtain a lead-based metal organic framework suspension; 1-5 g of modified phenolic resin is weighed and added into 20-50 mL of methyl alcohol, and a modified phenolic resin solution is obtained; slowly pouring the lead-based metal organic framework suspension into the methanol solution of the modified phenolic resin, and stirring the mixed solution for 30-60 minutes by using a magnetic stirrer, so that the lead-based metal organic framework is uniformly dispersed in the phenolic resin solution to obtain a lead-based metal organic framework-modified phenolic resin solution; the modified phenolic resin material provided by the invention not only can solidify waste oil, but also can play a role in adsorbing radioactive isotopes, and can effectively prevent leakage of radioactive waste oil.

The invention discloses a method and a device for improving an image frame rate. The method comprises the following steps: carrying out image acquisition and exposure according to a set pulse time sequence; in a set pulse time sequence, part of image exposure and collection frames are filtered out according to a preset interval so as to obtain image frames needing to be reserved; and compensating the filtered partial image exposure and acquisition frame to obtain a compensated image frame.

The present invention discloses an upright breast CT imaging device and a data acquisition method thereof, wherein the upright breast CT imaging device comprises: a bottom base, comprising a bottom base front base and a bottom base rear base; an upper base, located above the bottom base rear base, comprising an upper base front support and an upper base rear base; a rotating arm is installed on one side of the upper base front support, and a first synchronous transmission wheel, an encoder reader base, a slip ring device and a breast traction device are installed on the other side in sequence from bottom to top; a driving motor and a right-angle reducer and a second synchronous transmission wheel are installed on the upper base rear base; a scanning hole bracket is located above the bottom base front base. The upright breast CT imaging device provided by the present invention is small in size and can be continuously rotated 360 degrees. While achieving accurate positioning of the lesion, it greatly reduces the radiation dose.

The invention belongs to the technical field of heavy water reactor core flux detectors, and aims to solve the problems that the manual flux detector installation speed is low, the personnel irradiation dose is high, and the detector is easy to damage. The invention discloses a heavy water reactor core flux detector installation device and method, the device comprises a front guide pipe and a rear guide pipe which are coaxially arranged, the rear end of the front guide pipe is installed at a reserved installation position of a driving system shell, and a driving pair wheel set is arranged between the front guide pipe and the rear guide pipe; the driving pair wheel set is in transmission connection with the driving motor; the rear guide pipe is in butt joint with a detector reel bin, a reel is installed in the detector reel bin, the tail of the flux detector is clamped into the reel, and a flux detector cable is wound on the reel. According to the method, components of the device are used for installing the device, the heavy water reactor core flux detector installation device is removed, and flux detector installation is completed. The installation speed of the flux detector can be increased, the radiation dose of personnel is reduced, and the probability that the detector is prone to damage is reduced.

The invention provides a blind measurement method for an inner hole of an underwater vertical deep hole channel of a heavy water reactor. The blind measurement method comprises the following steps: establishing a measurement zero reference surface; a working platform is established by taking a measurement zero reference surface as a reference, and three references are carried on the working platform; establishing an axis system with the measurement zero reference surface on the working platform; measuring the distance between the pre-measuring hole and the measuring zero reference surface; and measuring the diameter of the pre-measuring hole, wherein the diameter value is equal to the outer diameter value of a certain step of the inner diameter gauge. The invention further provides a heavy water reactor underwater vertical deep hole channel inner hole blind measurement device which comprises a working platform, a measuring scale, a positioning gauge and an inner diameter gauge. The device can safely and accurately measure the inner diameter size of the vertical deep hole channel in the heavy water reactor underwater high-irradiation environment, realizes blind measurement of the inner hole of the vertical deep hole channel in nuclear power heavy water reactor high-irradiation, remote and underwater measurement, realizes accurate contact measurement, is high in accuracy, is far away from the high-irradiation environment to the greatest extent, and greatly reduces the irradiation dose of operators.

The utility model discloses a pickup device which is used for picking up a broken pin in a nuclear power station, the broken pin is located in a pin hole of a reactor core plate, and the pickup device comprises a base and a first collecting assembly. The base is suitable for being connected with the reactor core plate. The first collecting assembly comprises a first shell and a first cover which are connected with each other, and the first shell and the first cover jointly form a first containing cavity. The first collecting assembly comprises a first opening communicated with the first containing cavity, the first opening is formed in the bottom of the first collecting assembly, and the first shell is connected with the base. The first collecting assembly is configured to have a first state and a second state. In the first state, the first opening is exposed and is communicated with the pin hole. In the second state, the first opening is at least partially closed. The first cover body can move in the direction close to the first shell so that the first collecting assembly can be switched from the first state to the second state. The broken pin collecting operation of the picking device is convenient and fast, and the operation safety can be guaranteed.

The invention relates to the technical field of nuclear power overhaul, in particular to an online machining and repairing device for a nuclear reactor pressure vessel flange sealing surface. The device comprises a base mechanism, a main shaft rotating mechanism, a cutting arm beam and a dust collection mechanism, the base mechanism and the pressure vessel cylinder are coaxially arranged, and the base mechanism is supported on the inner wall of the pressure vessel cylinder; a hole structure is arranged in the center of the base mechanism; the main shaft rotating mechanism is adaptively connected with the hole structure of the base mechanism; the cutting arm beam is horizontally arranged and fixedly connected to the upper end face of the spindle rotating mechanism through a pressing plate, the spindle rotating mechanism drives the cutting arm beam to rotate, and a tool at the head of the cutting arm beam is driven to conduct online machining repair on the nuclear reactor pressure vessel flange sealing face. The shielding mechanism is located on the lower portion of the base mechanism, installed on the hanging basket supporting face in the pressure container and attached to the inner wall of a cylinder of the pressure container. The dust collection mechanism is connected to the side wall of the cutting arm beam, and the dust collection mechanism and the cutting arm beam rotate synchronously. According to the invention, the problem that online intelligent repair cannot be carried out on the flange sealing surface in the maintenance process of the reactor pressure vessel of the pressurized water reactor nuclear power station at present is solved, and the aim of ensuring the sealing performance and integrity of the pressure-bearing boundary of the primary loop through a reliable maintenance means is fulfilled.

This invention relates to the fields of brachytherapy and radiosensitization, specifically providing a... 125 I-nano implantable particles, their preparation methods, and applications. 125 The 1-nanometer implanted particles have a core-shell structure, consisting of a particle core and particles adsorbed on the outer surface of the particle core. 125 I and the particles encapsulated in the nucleus and 125 The outer shell of the I-type photosensitizer is a covalent organic framework. This invention... 125 The core of the I-nanometer implanted particle is used to enhance the energy deposition of gamma rays and X-rays, generating more hydroxyl radicals; the shell containing a type I photosensitizer is used to absorb the energy of Auger electrons and internal conversion electrons and excite the photosensitizer to generate singlet oxygen, effectively improving the response to... 125 The efficiency of I decay energy utilization. 125 I-nano implanted particles, combined with internal radiation therapy and radiodynamic therapy, destroy tumor cell DNA and cell membranes, enhance tumor killing and induce immunogenic cell death, thereby activating anti-tumor immunity and inducing remote effects.

The present invention belongs to the technical field of overpressure protection during the water pressure test of the primary circuit of a nuclear power plant, and specifically relates to a method for realizing simple and effective overpressure protection of the primary circuit water pressure test when the entire primary circuit needs a water pressure test after the overhaul of the nuclear power plant. The measurement signals of four pressure gauges are connected to the DCS signal acquisition cabinet, and the designed overpressure protection setting value is written into the DCS software. The DCS software processes and calculates the collected signals according to the overpressure protection setting value. When the measured pressure value exceeds the setting value, the pressure relief valve is opened to release the pressure or the water pressure test pump is shut down to prevent the primary circuit from overpressure; and a preliminary experiment of the water pressure test of the primary circuit is carried out. The present invention can avoid accidental pressure relief of the primary circuit due to malfunction of the protection system during overpressure or boosting of the primary circuit, which ultimately leads to water pressure failure of the entire primary circuit.

The invention discloses a controllable neutron and gamma generation device for nuclear logging, which can control a controllable neutron generation module to generate neutrons through a control instruction issued by an external upper computer according to logging requirements, and can generate neutrons, gamma and a neutron and gamma mixed field by controlling a LiH moderator, a first neutron absorber, a second neutron absorber and a gamma absorber. Compared with traditional natural source well logging, the method improves the radiation safety level of the nuclear well logging industry while improving the well logging efficiency, and reduces the radiation dose of workers.

The present disclosure relates to the field of image processing technology, and provides a training method, an identification method and a device for an elbow rotation axis recognition model. The method includes: obtaining a three-dimensional joint image, the three-dimensional joint image carries at least two joint rotation axis annotations marked by annotators; projecting the three-dimensional joint image and the joint rotation axis annotations it carries onto a two-dimensional image imaging plane to obtain a simulated two-dimensional image; performing image modality conversion on the simulated two-dimensional image to obtain a converted two-dimensional image; using the converted two-dimensional image to train an initial joint rotation axis recognition model until a preset training termination condition is reached to obtain a final joint rotation axis recognition model. The final joint rotation axis recognition model disclosed in the present disclosure can accurately identify the rotation axis position of a joint image taken by a patient in any posture, greatly reducing the difficulty of filming operations, and only requires one shot to meet the requirements, with simple operation, short time consumption and low radiation dose.

The invention belongs to the field of X-ray long-afterglow luminescent materials. The technical problems that traditional Pr < 3 + > doped fluoride is insufficient in afterglow performance, X-ray imaging depends on continuous irradiation, and color scattering noisy points exist are solved. The NaLuF4: Mg / Cs / Pr fluoride material is prepared by adopting a Cs < + >-Mg < 2 + > co-doping regulation strategy, the material is synthesized by an oleic acid-octadecene liquid phase method, and the X-ray excitation afterglow intensity of Pr < 3 + > is improved by about 110 times by utilizing the synergistic effect that Cs < + > enhances X-ray absorption and Mg < 2 + > optimizes a carrier shallow-deep trap level; the material is prepared into the high-light-transmittance rare earth nano flexible scintillation screen with the resolution ratio of 20.01 lp / mm. According to the invention, zero-noisy-point time-delay imaging after low-dose X-ray transient irradiation is realized, continuous irradiation is not needed, the radiation dose is lower, and the method is mainly applied to the field of X-ray time-delay imaging of low-dose medical diagnosis and industrial nondestructive testing. The method does not need continuous X-ray irradiation, and has important application value in the fields of medical diagnosis, industrial nondestructive testing and the like.

The invention discloses a CT (Computed Tomography) imaging method with constant image quality, which relates to the technical field of medical CT imaging and comprises the following steps of: 1, preparing a data set which comprises high-dose CT projections or images of a large number of patients and corresponding patient prior information; 2, constructing models including a dose estimation model, a scanning simulation model and an image reconstruction model; 3, training the model constructed in the step 2; 4, acquiring prior information of the patient; 5, obtaining the optimal examination dose of the patient by using the dose estimation model; step 6, executing CT scanning to obtain projection data of the patient; and step 7, obtaining a patient CT image with constant quality by using the image reconstruction model. The CT imaging method with constant image quality provided by the invention realizes the principle of reasonability, feasibility and as low as possible (ALARA) in radiation protection, can obtain the CT image with constant quality, and is beneficial to clinical diagnosis of the CT image.

The invention provides a clinical image-based cancellous bone mechanical property prediction method and system, and the method comprises the steps: carrying out the medical CT scanning of a plurality of prepared cancellous bone cubic samples, and obtaining the medical CT image data; carrying out segmentation processing on the medical CT image data, extracting a sample area and calculating an average HU value of a sample CT image; performing a uniaxial compression experiment on the sample, accurately measuring strain by using a digital image correlation method, and further obtaining a stress-strain curve to calculate an elastic modulus and compression strength; according to the average HU value and the corresponding mechanical index data, a linear relation model of the average HU value of the cancellous bone CT image and the elastic modulus and the compression strength of the cancellous bone is established, and then a personalized treatment scheme is formulated according to the characteristics of the cancellous bone of the patient. The method has high universality and accuracy, and the elastic modulus and the compression strength of the cancellous bone sample can be accurately measured.

This invention discloses a method and system for predicting kidney stone hardness based on cross-modal aligned knowledge distillation, comprising: training a teacher network using multi-channel DECT data, enabling the teacher network to predict stone hardness and extract the physical attribute vector Φ. DECT ;Φ DECT The dimension is d p Each dimension corresponds to a physical attribute that plays a decisive role in hardness prediction; a student network is constructed, which, after receiving a single-channel SECT image, first generates a latent physical attribute vector and then performs hardness prediction based on the latent physical attribute vector; an alignment loss is constructed, which, during the training of the student model, allows the distribution and geometry of to approximate Φ. DECT The SECT image to be predicted is input into the trained student model to predict the hardness of the kidney stone. This invention can transfer rich information from dual-energy CT to a plain CT model to improve the predictive ability of plain CT for kidney stone hardness.

The invention discloses a radiotherapy positioner and a preparation method thereof, and belongs to the technical field of medical materials. The radiotherapy positioner is a solid circular ring, a solid cylinder, a hollow circular ring or a hollow cylinder; the solid circular ring, the solid cylinder, the hollow circular ring or the hollow cylinder is composed of a carbon fiber composite material matrix and a heavy metal coating or a heavy metal carbide coating on the surface of the carbon fiber composite material matrix. The radiotherapy positioner has the characteristics of X-ray permeability, no artifacts during examination, strong development, light weight, good stability, good biocompatibility and the like, and can optimize the radiotherapy range, accuracy and use dosage to the greatest extent, so that the target area sketching is more accurate, and the injury of radiotherapy to a patient is reduced.

The invention relates to a micro-channel array type CsI: T1 scintillation screen and a preparation method thereof. The micro-channel array type CsI: T1 scintillation screen comprises a micro-channel array substrate; the micro-channel array substrate is of a channel structure, the channel structure is square holes, and the holes are vertically arranged in a square mode. The inner wall of a channel of the micro-channel array substrate is plated with a mirror surface metal reflecting film, and the channel is filled with a scintillator thallium-doped cesium iodide; and an aluminum film or a heavy metal film is evaporated on the incident surface of the micro-channel array CsI: T1 scintillation screen. The area of the channels of the scintillation screen relative to the surface of the base body is large, the larger the area ratio is, the larger the proportion of the scintillator is, the detection efficiency of the scintillation screen is better improved, and the radiation dosage of the back face is reduced. According to the scintillation screen, mirror surface metal such as an Al film is selected as the reflecting film, and the light output of the scintillation screen can be greatly improved. The test result shows that the X-ray detector integrated by the scintillation screen can realize the high spatial resolution of 101p / mm, and the effect is very excellent in the actual test.