118 results about "Doses rate" patented technology

The invention discloses an ultra-high dose rate radiotherapy plan optimization system based on compensator modulation, and relates to the technical field of radiotherapy. A data acquisition module is used for acquiring medical image data of a patient and receiving a clinical target; the clinical target comprises a target region prescription dose, an organ-endangering limit and a minimum dose rate threshold value required for triggering and maintaining a FLASH effect; and the FLASH biological effect evaluation module is used for calculating FLASH biological effective dose distribution corresponding to the physical dose distribution through an embedded biological effect model based on the input physical dose distribution and dose rate distribution. According to the method, the physical dose is converted into the accurate FLASH biological effective dose through the improved linear quadratic model embedded with the FLASH correction factor, the target tumor killing effect is guaranteed, normal tissue protection is enhanced with the help of the tissue differentiation correction factor, the industrial pain point that the physical dose reaches the standard but the biological effect does not reach the expectation is effectively solved, and the application prospect is wide. And the treatment plan better meets the clinical curative effect and safety core requirements.

The invention provides an interlocking protection optimization system and method of a FLASH accelerator and electronic equipment, and the system comprises an acceleration module which is used for generating an initial electron beam and accelerating the initial electron beam to obtain a high-energy electron beam; the beam quality guarantee module is in signal connection with the acceleration module and is used for monitoring, regulating and controlling the intensity and the position of the high-energy electron beam in real time; the treatment execution module is in signal connection with the beam quality guarantee module and is used for converting the high-energy electron beams into treatment rays and monitoring the output dose of the treatment rays in real time; and a safety interlocking protection module which is in signal connection with the acceleration module, the beam quality guarantee module and the treatment execution module and is used for collecting operation parameters of all parts of the FLASH accelerator in real time, performing analysis based on preset logic, triggering interlocking protection actions under abnormal working conditions, and controlling the treatment execution module to perform treatment. And active monitoring-intelligent analysis-rapid response closed-loop control of the ultrahigh dose rate radiotherapy accelerator in a full operation period is realized.

The invention relates to the technical field of accelerator radiation protection, in particular to an induced radioactivity assessment method suitable for a mobile accelerator component. Monte Carlo simulation software is adopted to calculate radionuclide activity concentrations in different areas of an acceleration component before movement, then radionuclides serve as radiation source items, and three-dimensional space dose rate distribution of the component and the periphery when the position of the accelerator component changes is obtained through calculation. And rapid evaluation of the received dose of the staff during maintenance and rapid formulation of a maintenance scheme are realized. The method effectively promotes the application of the Monte Carlo method in the field of radiation protection of the accelerator, provides reference for radiation hazards to workers, and provides technical support for radiation protection and operation maintenance of the accelerator.

Radiotherapy is the most widely used and effective anti-tumor therapy, however it can damage healthy tissues surrounding the tumor. One approach to reducing damage to healthy tissue involves irradiation at dose rates far exceeding those currently used in clinical contexts reduces radiation-induced toxicities while maintaining an equivalent tumor response. This is known as the FLASH effect. The mechanism responsible for reduced tissue toxicity following FLASH radiotherapy (FLASH-RT) is still undetermined; multiple hypotheses have been suggested by linking the high dose rate to rapid oxygen depletion, immune response, reduction of peroxyl radical lifetime, preservation of normal tissue stem cells, etc. While effective, proton therapy is underutilized, contributing to fewer than 2% of all external beam radiation treatments. To overcome this shortcoming, provided are methods which utilize the highest energy layer and a universal range shifter (URS) to facilitate rapid spot arc therapy (RAPIDSPARC™).

The invention relates to the technical field of medical X-ray, radio frequency and high-frequency diagnosis and treatment equipment, in particular to a full-static X-ray radiotherapy system and method. The system is composed of an electron source, an accelerating cavity, a two-dimensional deflector, an annular magnet set, a strip-shaped anode target, a multi-leaf collimator set, a vacuum cavity and the like. The electron beam enters the two-dimensional deflector after being accelerated, and any plane angle is obtained under the pure electromagnetic action; and then the X-rays are guided to the strip-shaped anode target along each electron channel in an annular magnetic field of the annular magnet group to bombard and generate the X-rays. The multi-leaf collimator performs spatial modulation on rays to form an irradiation field matched with a target region, so that multi-angle high-precision radiation irradiation without mechanical rotation is realized. The strip-shaped target surface increases the heat dissipation area and cooperates with an efficient cooling loop, so that the dose rate upper limit is improved, and the FLASH radiotherapy requirement is met. The scheme is compact in structure, low in cost and simple and convenient to maintain, overcomes the defects of large size, low efficiency, limited dosage and the like of traditional rotary radiotherapy equipment, and has wide clinical popularization value.

The invention provides an accelerator system adjustment method, an accelerator system, electronic equipment and a storage medium. The transmission characteristic data and the charge quantity data of the undeflected beam are obtained through the first beam position detector, and the form and the charge quantity of the undeflected beam are accurately adjusted in combination with a preset adjustment strategy, so that the stability of beam transmission is ensured. And after the form data of the first beam reaches a preset value, monitoring the deflected beam data by using a second beam position detector, and further accurately adjusting the accelerator system to ensure that the deflected beam conforms to the target transmission characteristics. According to the invention, the transmission state of the beam can be accurately controlled in real time, risks of vacuum box breakdown and the like caused by beam mismatch are avoided, the safety and the stability of the system are improved, the possibility of equipment damage is obviously reduced especially under the high-dose-rate transient beam, and the treatment effect and the continuity of Flash radiotherapy are guaranteed.

The invention relates to a nuclear medicine medication nursing radioactive operation safety warning and evaluation system. The system comprises a sensing acquisition module, a behavior identification module, a dose evaluation module, a risk evaluation module, a risk grade division module, a warning and intervention module, a data storage and tracing module and a self-adaptive learning module. The system can collect parameters such as environment dose rate, individual dose rate, operation distance and time in real time in the processes of nuclear medicine preparation, split charging, injection and waste liquid disposal, analyze operation behaviors of nursing personnel in combination with action recognition results, dynamically calculate accumulated dose, and improve the accuracy of the operation of the nursing personnel. Risk indexes are constructed by comprehensively considering factors such as dosage ratio, liquid medicine residue activity and violation probability, and graded early warning is carried out; when the risk level exceeds a threshold value, triggering acousto-optic and terminal prompt, and generating an operation log for tracing; the system has data storage and self-adaptive optimization functions at the same time, model parameters can be corrected according to historical risk data, and long-term dynamic optimization is achieved.

This invention discloses a method for estimating radioactive release during the preparation of radioactive metal waste, comprising the following steps: (1) conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; (2) setting up monitoring points in the radioactive metal waste areas with different pollution levels, and calculating the radioactive residue in the metal waste based on the monitoring data; (3) calculating the total release of each nuclide in the metal waste based on the above-mentioned radioactive residue in the metal waste and the obtained concentration data of radionuclides in the metal waste. By conducting gamma dose rate surveys and delineating the distribution of radioactive pollution in the radioactive source area; setting up monitoring points in the delineated areas to obtain the radioactive residue in the metal waste; and calculating the total release of each nuclide using formulas, the process is simple, easy to operate, and can obtain effective data on the total release of nuclides, providing data support for the preparation of radioactive contaminated metal waste and supporting the assessment of the dose caused by contaminated metal waste to the public.

A medical linear accelerator configured to operate in radiotherapy may have an electron gun for emitting an electron beam. An accelerator waveguide accelerates the electron beam. A linear accelerator head defines an inner beam passage for directing the electron beam. A beam current transformer in the linear accelerator head is for monitoring the electron beam An electrostatic shield is provided in the inner beam passage, the electrostatic shield being positioned downstream of the beam current transformer for shielding the beam current transformer.

The invention relates to the field of gamma dose rate monitoring, and provides a high-altitude radioactive point source dose rate distribution analysis method and system, and the method comprises the steps: collecting original counting data and energy spectrum data, and obtaining environment parameter data and flight carrier position information; performing statistical calculation on the original counting data to obtain counting statistical parameters; performing nonlinear correction on the original counting data, the energy spectrum data, the environmental parameter data and the counting statistical parameters to obtain corrected detector data and measurement uncertainty; performing fusion calculation on the corrected detector data to obtain a fusion weight, and performing verification processing to obtain fusion dose rate data; performing prediction processing on the fused dose rate data and the environmental parameter data to obtain a range switching signal; and performing reconstruction processing on the fused dose rate data, the range switching signal, the measurement uncertainty and the flight carrier position information to obtain ground dose rate distribution data. According to the invention, the accuracy and reliability of high-altitude radioactive point source dose rate distribution analysis are improved.

The embodiment of the invention provides an energy response compensation method of a dose rate value and a chip. The energy response compensation method of the dose rate value comprises the following steps: acquiring the number of pulses generated by radioactive rays in each energy response compensation area; and according to each pulse number and the weight corresponding to each energy response compensation area, obtaining a dose rate value after energy response compensation. The dose rate value energy response compensation method provided by the embodiment of the invention is relatively high in accuracy.

As the ion beam is accelerated, the radius of the spiral orbit gradually increases, and the center of the spiral orbit moves in the predetermined radial direction of the gap toward the direction close to the peripheral portion, and then the moving direction of the spiral orbit is reversed and further moves toward the center of the gap. To achieve this, the intensity distribution in the orbit plane of the main magnetic field is designed. Thus, as a small accelerator capable of changing the energy of the extracted beam, the efficiency of beam injection from the external ion source into the accelerator is improved, and as a result, the dose rate of the extracted ion beam is improved.

The invention relates to the related technical field of measurement and calibration, in particular to a signal processing and calibration method and device for a long-rod type gamma dose rate instrument and a medium. The method comprises the following steps of: acquiring a real-time electric signal generated by the long-rod type gamma dose rate instrument by adopting a multi-sampling method, and converting the electric signal into a pulse signal; carrying out noise removal processing and abnormal value elimination processing on the pulse signals, and carrying out summary analysis to obtain a target pulse number; environment information and information of the long-rod type gamma dose rate instrument are collected, and a preset coefficient is corrected based on the environment information and attitude information of the long-rod type gamma dose rate instrument; calculating a ratio between the preset coefficient and the target pulse number; the ratio is gamma dosage rate. Through the arrangement, the obtained measurement result is more accurate.

The utility model provides an X-ray adjusting device and X-ray radiotherapy equipment for animal experiments, and the device comprises a fixed plate which is used for being fixed with an X-ray accelerator; the dose adjusting assembly is arranged on one side of the fixing plate, the dose adjusting assembly is telescopic, and the dose and the dose rate are changed through stretching of the dose adjusting assembly. The dose and the dose rate of the X-rays can be changed by adjusting the length of the dose adjusting assembly.

The present disclosure provides a rack for radiotherapy equipment and a radiotherapy equipment. The rack for radiotherapy equipment comprises a supporting assembly, a drum configured in a horizontal structure, having an axial first end and a second end, both of which are rotatably arranged on the supporting assembly, and a carrier arranged on the outer wall of the first end and adapted to carry an external pulse transformer so that the pulse transformer rotates synchronously with the drum. The drum is adapted to provide a reliable mounting platform for a super high dose rate radiotherapy equipment, so that the particle rays output by a plurality of beam modules configured on the super high dose rate radiotherapy equipment can be accurately converged in the drum. Both the first end and the second end of the drum are rotatably arranged on the supporting assembly to meet the bearing capacity requirements of the drum and other components arranged thereon, so that the rack for radiotherapy equipment forms a reliable mounting platform. The carrier is used to assemble the pulse transformer on the drum and synchronize with the drum.

The invention relates to the technical field of nuclear radiation detection, in particular to a portable pulse X-ray dose rate meter and a detection method. The probe module is used for simultaneously acquiring dose information and time information of pulse X-rays; the circuit processing module is connected with the probe module and used for collecting and processing probe signals; and the host module is in communication connection with the circuit processing module and is used for setting parameters, receiving data, analyzing dosage and outputting a detection result dosage value. The invention designs a portable pulse X-ray dose rate instrument, which can measure a pulse X-ray dose rate value with short pulse time and high instantaneous dose rate in a radiation field, meet the calibration requirement of a nuclear critical accident alarm system, ensure the safety of facilities and personnel and promote the research and development of working measuring instruments.

A system for mapping oxygen levels in tumors includes a needle that is sized to deliver high dose rate brachytherapy to tissue into which the needle is inserted, where the needle includes a radio frequency micro-coil sensor positioned within a shaft of the needle and a spin probe mounted to an outer surface of the shaft of the needle. A processor is in communication with the needle and configured to move the radio frequency micro-coil sensor along the shaft of the needle. The processor is also configured to receive, from the radio frequency micro-coil sensor, oxygen level readings at a plurality of tissue locations along the shaft of the needle. The processor is also configured to generate an oxygen level mapping of the tissue based on the oxygen level readings received from the radio frequency micro-coil sensor.

This invention discloses a miniature extrapolation ionization chamber and method for measuring the surface absorbed dose rate of a β-adhesive patch, relating to the field of dose rate technology. The ionization chamber includes a front end and a shell. A micrometer's rotating handle is located at the rear end of the shell, and a micrometer screw extends into the shell. The front end includes an entrance window, which is fixed to the front end face of the shell by a tissue equivalent material pad. A protective ring is disposed around a collecting electrode, which is coaxially positioned inside the shell, with its rear end connected to the front end of the micrometer screw. An insulating gap is formed between the collecting electrode and the protective ring. The entrance window, collecting electrode, and protective ring together constrain the formation of a sensitive volume. The depth of the sensitive volume is changed by adjusting the distance between the collecting electrode and the entrance window using the micrometer. The ionization chamber and method provided by this invention can quickly and effectively calibrate and measure the surface absorbed dose rate of small-area β-adhesive patches.

The present invention discloses a neutron radiation-proof glass and a preparation method thereof. The neutron radiation-proof glass comprises, by weight, the following components: SiO2: 0.5-3.5%; B2O3: 20.0-35.0%; Li2O: 0.5-9.0%; Na2O: 0.1-5.0%; Gd2O3: 31.0-40.0%; Y2O3: 11.0-19.0%; GeO2: 0.1-9.0%; Nb2O5: 0.1-5.0%; ZnO: 0.5-5.0%; CeO2: 1.0-9.0%; WO3: 0.5-5.0%; and In2O3: 1.0-2.0%. By rationally configuring the components and their contents, the present invention achieves a 550nm transmittance greater than 80% and a Knoop hardness greater than 600×10 7 MPa, the glass thickness required to reduce the neutron dose rate to 50% is less than 30 mm, and the neutron radiation-proof glass of the present invention can effectively protect against neutron radiation. The obtained neutron radiation-proof glass has good radiation protection, glass forming properties, and chemical stability, and the optical uniformity of the neutron radiation-proof glass can reach 5×10 ‑6 , it is easy to prepare large-sized and highly uniform neutron radiation-proof glass.

1. The name of the design product: personal dosimeter. 2. The use of the design product: the design product is used for monitoring the personal cumulative dose and dose rate caused by X and γ radiation in the nuclear radiation environment. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: front view.

The application discloses an anti-radiation sensor, which comprises a sensor body, a base fixedly connected to the bottom of the sensor body, and a sensing surface on the top of the sensor body; and an anti-radiation assembly surrounding the side surface of the sensor body, which comprises, from inside to outside, a heat insulation layer, an anti-radiation layer and a protective shell. The application provides an anti-radiation sensor, which can reduce the influence of external radiation on the sensor by arranging the anti-radiation assembly outside the sensor body, so that the sensor can normally work in a high-dose-rate and high-cumulative-dose radiation environment, and stable operation of the sensor is ensured.

The present application relates to the technical field of accelerator radiation protection, and particularly relates to a method for evaluating induced radioactivity suitable for mobile accelerator components; the method is characterized in that the activity concentration of radionuclides in different regions of the accelerator components before movement is calculated by using Monte Carlo simulation software, then the radionuclides are taken as radiation source terms, and the three-dimensional spatial dose rate distribution of the components and the periphery when the position of the accelerator components changes is calculated, so that the rapid evaluation of the dose received by the staff during maintenance and the rapid formulation of the maintenance scheme are realized. The method effectively promotes the application of the Monte Carlo method in the field of accelerator radiation protection, provides a reference for the radiation hazards received by the staff, and provides technical support for the radiation protection and operation and maintenance of the accelerator.

1. Name of the product in this design: Handheld radionuclide identifier. 2. Application of this design: This design is used for the detection of radioactive materials, dose rate measurement, and identification of radionuclides. 3. The key design feature of this product is its shape. 4. The image or photograph that best illustrates the design's key points: a 3D model. 5. The bottom surface of this product is a part that is not easily seen or cannot be seen during use, so the bottom view is omitted.

The invention discloses a state monitoring and early warning method and device for a pressure transmitter, and the method comprises the steps: obtaining the gamma-ray dose rate and the temperature and humidity of the current environment of the pressure transmitter; inputting the gamma ray dose rate and the temperature and humidity into a trained irradiation damage coupling model to obtain the irradiation damage amount of the pressure transmitter; inputting the irradiation damage amount, the current output signal of the pressure transmitter and the historical measurement precision calibration value into a precision prediction model to obtain the future measurement precision of the pressure transmitter; the future measurement precision is used for indicating the performance state of the pressure transmitter; and according to the future measurement precision, determining an early warning level of the pressure transmitter, and executing a corresponding early warning operation based on the early warning level. Therefore, the early warning precision of the pressure transmitter is improved.

Radiotherapy is the most widely used and effective anti-tumor therapy, however it can damage healthy tissues surrounding the tumor. One approach to reducing damage to healthy tissue invoves irradiation at dose rates far exceeding those currently used in clinical contexts reduces radiation-induced toxicities while maintaining an equivalent tumor response. This is known as the FLASH effect. The mechanism responsible for reduced tissue toxicity following FLASH radiotherapy (FLASH-RT) is still undetermined; multiple hypotheses have been suggested by linking the high dose rate to rapid oxygen depletion, immune response, reduction of peroxyl radical lifetime, preservation of normal tissue stem cells, etc. While effective, proton therapy is underutilized, contributing to fewer than 2% of all external beam radiation treatments. To overcome this shortcoming, compact radiotherapy systems are provided that incorporate multi-function components, reducing bot equipment size and expense.

This application provides a situational fusion analysis method and system for nuclear radiation monitoring, relating to the field of data processing. In this method, a unified situational awareness session is constructed for nuclear radiation monitoring. Multi-node observation data is aligned using time window identifiers and spatial grid identifiers to form a grid observation package containing gamma dose rate, energy spectrum, nuclide activity concentration, and environmental information. Based on this, each situational node is driven to generate interpretative fragments such as propagation, shielding, background, and source terms. Candidate situational puzzles are assembled through complementary and coupling relationships, and verifiable traces are generated in reverse. By combining trace inquiry and cross-node evaluation to identify consistency illusions, multi-world situational branch construction is triggered, and private perturbation signatures are used to suppress the dominance of homogeneous nodes, thereby outputting a fusion result containing situational puzzles, evidence strength, and discrimination gaps. Implementing the technical solution provided in this application facilitates improved accuracy of situational fusion analysis in complex and atypical scenarios of nuclear radiation monitoring.

According to the radioactive hydrogel and the preparation method and application thereof and the radioactive tumor treatment application, chitosan serves as a matrix and is crosslinked with genipin to construct a three-dimensional network, and stable loading and slow release of radionuclides can be synchronously achieved; the self-antibacterial and adhesion characteristics of the patch can reduce the infection risk and ensure the fixation of the patch, so that a safe, effective and easy-to-operate local treatment platform is provided, the prepared patch can be directly placed on a tumor bed after resection in an operation, beta or alpha rays released by radionuclides accurately and continuously act on an area where tumor cells are most likely to remain, and the effect of treating the tumor cells is achieved. Different from traditional external radiation radiotherapy, the hydrogel can continuously release radiation with a low dosage rate. The mode has a stronger biological effect (such as inhibition of reproliferation) on tumor cells, the radiosensitivity difference of different cell periods and time phases can be overcome, the killing effect is more thorough, and chitosan is proved to have certain antibacterial activity, tumor cell growth inhibition activity and immunomodulatory activity. A synergistic effect can be generated with radionuclide, and a microenvironment which is not beneficial to survival and relapse of tumor cells is constructed together with the radionuclide.

The invention provides a wide-energy-spectrum neutron dose rate meter, and the meter comprises a mechanical structure assembly which comprises a proportional counter tube, a neutron moderator layer, and a neutron multiplier layer; wherein the neutron moderator layer wraps the proportional counter tube, and the neutron multiplier layer is arranged between the neutron moderator layer and the proportional counter tube; and the circuit board is used for providing working voltage for the proportional counter tube and processing a detection signal output by the proportional counter tube.

The application provides a voxel-level radionuclide dose estimation method based on radionuclide imaging and a computer device. The method comprises the following steps: acquiring X-ray structural images and gamma-ray functional images at a single time point or multiple time points; segmenting a region of interest to obtain multiple sub-regions of interest; performing regional partial volume correction on the multiple sub-regions of interest of the gamma-ray functional images to obtain corrected gamma-ray functional images; performing registration on the corrected gamma-ray functional images; performing activity-dose rate conversion on the registration results to obtain a dose rate, and performing voxel-level curve fitting and integration on the dose rate to obtain an absorbed dose distribution result, and determining the absorbed dose of each sub-region of interest based on the absorbed dose result. The application can reduce the influence of the partial volume effect on the resolution of radionuclide imaging, improve the accuracy of radionuclide image registration, and further improve the accuracy of radionuclide absorbed dose estimation.

This invention relates to the field of target box transportation technology after heavy water reactor irradiation. Addressing the problem that existing transportation channels cannot effectively reduce radiation exposure to personnel during the transportation of radioactive target boxes, this invention provides a target box transportation device after heavy water reactor irradiation, comprising a transportation pipe, a shielded transfer container, and a conveyor belt. A negative pressure is established within the transportation pipe to draw the target box into a vertical section. A separator is installed on the vertical section of the transportation pipe to allow the target boxes to enter the shielded transfer container one by one within a shielded box. The shielded transfer container is transported via the conveyor belt. Furthermore, this invention also provides a method for transporting target boxes after heavy water reactor irradiation, sequentially loading the target boxes from the vertical section into designated positions within the shielded transfer container in the shielded box, and completing radiation protection treatment of the target boxes within the shielded box. By loading the irradiated target boxes into a shielded working box, compared to containerized transport, the dose rate in the operation and maintenance area can be reduced from 2 mSv / h to 25 μV / h, significantly reducing the dose level for operators.