73 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.

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™).

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.

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 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.

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 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.

1. Name of the product in this design: Nuclear Radiation Detector. 2. Purpose of this design: To detect the dose rate of ionizing radiation in the environment and objects. 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.

The application belongs to the technical field of medical devices, and relates to a ring-shaped beam irradiation method and system for radiotherapy. The application provides a ring-shaped beam irradiation system for ultra-high dose rate radiotherapy, which comprises an electron beam generating device, a beam focusing and transmission system, an initial beam deflection system, a main ring beam deflection system and a beam blocker; wherein the electron beam deflection system comprises a 90-degree combined deflection assembly comprising a Kicker magnet. The control method of the application comprises: dynamically scheduling the magnetic field of each Kicker at a millisecond level through electromagnetic control, realizing instant extraction of the beam at any predetermined angle on the ring-shaped main beam line, and completing multi-angle irradiation without mechanical movement and delay. The system can be expanded into a multi-treatment room system sharing the same accelerator. The application realizes an ultra-high dose rate radiotherapy platform with small floor area, short treatment time and sustainable upgrade, and is suitable for next-generation precise radiotherapy.

The application relates to a nuclear power plant accident solution analysis method, device, equipment and storage medium, comprising the following steps: determining the total reaction surface area of silver particles in a solution in a current period based on a first parameter of the silver particles, a second parameter of silver iodide and a solution volume in the current period; determining the generation amount of silver iodide in the solution in the current period according to the total reaction surface area of the silver particles in the solution, inherent properties, a first chemical reaction rate constant of the solution and the solution volume; determining the decomposition amount of the silver iodide in the solution in the current period according to the dose rate of a pool in a containment and a second chemical reaction rate constant of the solution; and determining the residual amount of the silver iodide based on the generation amount and the decomposition amount of the silver iodide in the solution in the current period. Compared with the result obtained by manual estimation, the application is more efficient and more accurate.

This disclosure relates to a method for determining bioeffective dose, wherein the method includes: detecting the boron concentration C of each voxel in the target at multiple time points. B ; Calculate C B The corresponding biological effect value (RBE) B Determine C B and RBE B The first association relationship, based on the first association relationship, determines the connection through C. B Characterized RBE B ; Calculate C B The corresponding first physical absorbed dose rate D B And other physical absorbed dose rates corresponding to dose components other than boron, and physical dose rate distribution D phy According to RBE B and D B The product of the other dose components and the product of other biological effect values ​​and other physically absorbed dose rates is used to calculate C. B The combined biological effect value (CBE); based on CBE and D phy Calculate the biologically effective dose D bio According to this disclosure, it is beneficial to determine the appropriate irradiation time for different voxels during BNCT in order to obtain better therapeutic effects.

A method of measuring and optimizing dose rate variation in an ion implantation system, the method including generating a scanned beam according to a beam recipe provided to the ion implantation system, moving a profiler head across the scanned beam, the profiler head including a current sensing array including at least one current sensing device adapted to measure a dose rate of the scanned beam for generating a scanned beam profile of the scanned beam, identifying peak current values across the scanned beam profile and deriving a first dose rate profile therefrom, comparing at least one metric associated with the first dose rate profile to at least one corresponding dose rate variation target to determine whether the first dose rate profile is sufficiently uniform, and if the first dose rate profile is not sufficiently uniform, adjusting settings of the beam shaping components so that the scanned beam has a second dose rate profile that is more uniform than the first dose rate profile.

The utility model discloses a neutron dose rate monitoring auxiliary device which comprises a box body, one side of the top of the box body is rotatably connected with a top cover through a hinge, a partition plate is fixed in the box body and divides the interior of the box body into two containing cavities, a pressing assembly is installed on the lower surface of the top cover, and the pressing assembly is connected with the top cover through a hinge. Two side plates are fixed to one side of the outer side wall of the box body, and a mounting assembly is rotationally connected between the two side plates. According to the neutron dose equivalent rate instrument, the box body, the top cover, the pressing assembly and the mounting assembly are arranged, when not used, the neutron dose equivalent rate instrument can be stored in the box body and extruded and fixed through the pressing assembly, shaking of the neutron dose equivalent rate instrument in the box body is avoided, and when needing to be used, a host of the neutron dose equivalent rate instrument can be placed on the surface of the top cover; the positioning sleeve is used for positioning and fixing the neutron dose equivalent rate, and the handheld operating handle is fixed through the mounting assembly, so that the neutron dose equivalent rate is more convenient to use.

The invention relates to the technical field of nuclear, and discloses a site dose rate measuring device and method. According to the site dose rate measuring device provided by the invention, a physical barrier is constructed through the sleeve pre-embedded in the outer wall of the structure and the closed blind end of the sleeve, a high-dose site is isolated from an external overhaul site, and during measurement, a probe of a monitor only needs to be inserted from the outside through a measuring channel opened by a shielding compensation structure; a worker does not need to carry equipment to enter or get close to a high-dose place, temporary perforation is not needed during measurement, and aerosol disturbance, equipment surface contamination diffusion (cross contamination) and direct external irradiation and internal irradiation risks borne by the worker which are possibly caused by the fact that the worker enters the place during operation are completely eradicated. Meanwhile, as the blind end extends into the high-dose place, the detector completely penetrates through the structural wall body, the radiation field of the place to be detected is directly detected, the dose rate of the real place which is not additionally attenuated by the wall body is measured, and the data is more accurate.

The application discloses a kind of radioactive process system leakage monitoring methods, according to the dose rate level value of acquisition judges whether leakage occurs;And according to the typical nuclide spectrum analysis data of acquisition inversion leakage source item in the space to be measured, the activity concentration of typical radioactive nuclide in the space to be measured is obtained.The radioactive process system leakage monitoring method of the application strictly monitors leakage situation, so that relevant personnel can respond in time.The application also discloses a kind of radioactive process system leakage monitoring equipment.

The invention relates to the technical field of radiation experiment measurement equipment, in particular to a low background experiment measurement device and a low background experiment system. The low background experiment measuring device comprises a main shell, a plurality of shielding layers and a plurality of shielding layers, wherein the plurality of shielding layers are encircled in the main shell to form a background shielding space; the diaphragm is arranged on the main shell and is coaxial with a beam outlet of a radioactive source of the low-background experiment system, and the diaphragm is suitable for introducing an external radioactive source into a detection area in the background shielding space in a collimation manner and providing different low-range dose rates for the interior of the device by virtue of a plurality of radioactive sources; the three-dimensional positioning mechanism is installed in the background shielding space and is suitable for driving the instrument to be detected to move into the detection area. The device can actively shield a natural background, reduce the interference of the natural background on the measurement of a low-range instrument, improve the measurement precision of the instrument, and realize the reliable measurement of an ionizing radiation low-background experiment; the device also can accurately adjust the measurement position of the instrument to be measured, thereby improving the measurement efficiency, precision, operability and safety.

A treatment planning tool to automate the optimization of parameters to achieve the intended dose and dose rate available using Ultra-High Dose Rate (UHDR) pulsed electron accelerators. Aspects of the disclosure provide a tool that makes the search of optimal machine parameters less burdensome and eliminate potential user errors by automating this process. Commercial electron FLASH platforms deliver UHDR doses at discrete combinations of pulse parameters including pulse width (PW), pulse repetition frequency (PRF) and number of pulses (N), which dictate unique combinations of dose and dose rates. Additionally, collimation, source to surface distance (SSD), and airgaps also vary the dose per pulse. The present disclosure presents a pulse parameter optimizer application to match intended dose and dose rate precisely and efficiently.

The application discloses a kind of measurement method and device of organic phase sample, method includes: determining uranium series working standard solution and plutonium series working standard solution;According to uranium series working standard solution and plutonium series working standard solution, measurement and respectively obtain uranium standard X-ray absorption spectrum and plutonium standard X-ray absorption spectrum;According to uranium standard X-ray absorption spectrum, calculate and obtain uranium standard natural logarithm value, according to plutonium standard X-ray absorption spectrum, calculate and obtain plutonium standard natural logarithm value;According to uranium standard natural logarithm value and the uranium concentration of uranium series working standard solution, obtain uranium working curve, according to plutonium standard natural logarithm value and the plutonium concentration of plutonium series working standard solution, obtain plutonium working curve;According to uranium working curve and plutonium working curve, measure organic phase sample.The scheme of the application does not need to prepare organic phase standard solution, carries out the measurement of organic sample, reduces standard consumption and workload, reduces the contact time with radioactive materials, reduces the dose rate level of operator.

1. The name of the design product: slice type aerosol radiation dose rate automatic detector. 2. The use of the design product: the design product is used for accurate measurement of atmospheric aerosol radionuclide. 3. The design points of the design product: in shape. 4. The picture or photo that best indicates the design points: perspective view 1.

The invention discloses an intelligent radioactive waste collecting device for a nuclear power station. The intelligent radioactive waste collecting device comprises a barrel body module, an information collecting and networking module, an automatic cover opening and closing control module, a camera monitoring module, a dose rate measuring module, a color customization module and a double-power-supply module. The barrel body module comprises a barrel body, a barrel cover and an internal control box, a main control board PCBA is arranged in the control box, a main control MCU chip is arranged on the main control board PCBA, and the main control MCU chip is electrically connected and communicated with the information acquisition and networking module, the automatic cover opening and closing control module, the camera monitoring module, the dose rate measurement module and the dual-power supply module to realize signal transmission and cooperative control; the radioactive waste collection process comprises the steps of preparation stage, information collection, color recognition, dose rate measurement module detection, automatic cover opening, delivery completion and exception handling.

A low-pressure ionization chamber, a design method, and a medical linear accelerator. The low-pressure ionization chamber comprises a housing (100). A closed chamber is formed inside the housing (100), and a low-pressure environment lower than the standard atmospheric pressure is formed in the closed chamber, so that the ion recombination ratio of positive and negative charges is not greater than 0.01, thereby improving collection efficiency of positive and negative charges, and solving the technical problem in the existing technology of inaccurate monitoring results at an ultra-high dose rate due to the influence of ion recombination on a penetration-type air ionization chamber.