80 results about "Particle transport" patented technology

The invention discloses a radiator micro-channel structure integrity detection method based on acoustic measurement, and relates to the technical field of information, the method couples acoustic propagation measurement with density inversion and particle transport observation, firstly screens a key observation object according to density gradient change, and then constructs a hydrodynamic equilibrium graph by using auxiliary particle flow, and finally obtains the structural integrity of the radiator micro-channel. And channel-by-channel difference is carried out with reflection measurement of standard acquired data, so that defects are indicated by three domains of energy, time and space together. According to the closed-loop link, the sensitivity to tiny blockage, slight deformation and early crosstalk is remarkably improved, the false alarm rate that single measurement is easily influenced by noise and working condition fluctuation is reduced, fine positioning of channel-level abnormal positions and ranges is achieved, and the closed-loop link is suitable for high-resolution detection of dense micro-channel arrays without disassembly or destructive operation.

The invention discloses a BNCT dose calculation method, which comprises the following steps: S1, constructing a voxel model, initializing one or more particles in a simulation system, and respectively acquiring the initial position, energy and movement direction of each particle; s2, adaptively selecting a Monte Carlo particle tracking algorithm and a flux counting mode based on the region where the particles are located and the energy of the particles; s3, repeating the step S2 until the particles leave the simulation system or are killed when meeting a truncation condition; and S4, cumulatively calculating dose distribution. Through the BNCT dose calculation method, the Monte Carlo particle transport simulation time is greatly shortened, the BNCT dose calculation efficiency is optimized, and the method is suitable for rapid and high-precision radiation dose simulation under a BNCT complex tissue structure.

The invention discloses a macro-micro hybrid simulation method for electrical equipment insulation defect analysis, which comprises the following steps: S1, establishing a gas defect discharge process simulation model, and describing microscopic particle state change and electric field distribution in a gas discharge process through a particle transport equation and a Poisson equation; the method comprises the steps of S1, establishing an electromagnetic propagation process simulation model, and describing the propagation process of an electromagnetic signal generated by gas discharge through a Maxwell equation set, and S3, performing joint simulation on the model, taking equivalent current of gas discharge as an excitation source, simulating propagation of the electromagnetic signal in power equipment through a finite time domain difference method FDTD, and recording a signal value of a receiver. According to the macro-micro hybrid simulation method for analyzing the insulation defects of the power equipment, the insulation defects of the power equipment are accurately analyzed and monitored, important support is provided for state monitoring and maintenance of the power equipment, and digital transformation of the monitoring technology of the power equipment is promoted.

A computer-implemented method is disclosed for designing magnetic field geometries in magnetically confined plasmas, such as stellarators, to minimize energy or particle transport due to plasma turbulence. The method utilizes machine learning (ML) models trained on datasets of gyrokinetic simulations. These models predict turbulent transport based on geometric features derived from the magnetic configuration, which influence solutions of the gyrokinetic equation in ballooning representation. The input features include both raw geometrical quantities-such as field strength, curvature drifts, and perpendicular wavenumbers-and engineered features derived therefrom. The models may incorporate translational invariance and be implemented as convolutional neural networks or via solutions to parameterized differential equations. The resulting ML-driven target functions are computationally efficient and suitable for use in optimization algorithms to identify magnetic geometries that enhance plasma confinement.

A computer-implemented method is disclosed for designing magnetic field geometries in magnetically confined plasmas, such as stellarators, to minimize energy or particle transport due to plasma turbulence. The method utilizes machine learning (ML) models trained on datasets of gyrokinetic simulations. These models predict turbulent transport based on geometric features derived from the magnetic configuration, which influence solutions of the gyrokinetic equation in ballooning representation. The input features include both raw geometrical quantities—such as field strength, curvature drifts, and perpendicular wavenumbers—and engineered features derived therefrom. The models may incorporate translational invariance and be implemented as convolutional neural networks or via solutions to parameterized differential equations. The resulting ML-driven target functions are computationally efficient and suitable for use in optimization algorithms to identify magnetic geometries that enhance plasma confinement.

The invention relates to an aerosol particle scattering characteristic experimental platform and experimental method based on a Pockels effect, and belongs to the technical field of optical measurement. The experimental platform comprises an optical platform, an aerosol particle transport system, an optical path system and a data processing system, the aerosol particle conveying system comprises a combustion chamber, a dust aerosol generator, a water mist aerosol generator, a pipeline and an aerosol jet hole; the combustion chamber, the dust aerosol generator and the water mist aerosol generator are all placed outside a room where the optical platform is located, and the light path system is placed on the indoor optical platform; all parts of the data processing system are placed inside or on the top of the cabinet, and the cabinet is close to the optical platform. According to the aerosol particle scattering characteristic experiment platform based on the Pockels effect, the electro-optical modulator based on the Pockels effect and the phase-locked demodulation technology are used, the Mueller matrix measurement time can be shortened, and the measurement precision is improved.

The application provides a heat pipe micro reactor steady-state multi-physical coupling method and system based on a fission response function, which integrates a fission response function physical program, a self-developed Unifoam finite element thermal program and a heat pipe program, realizes steady-state joint solution of three physical fields of nuclear neutronics, solid thermal engineering and heat pipe two-phase flow through a coupling iterative driving script, and obtains accurate power field and temperature field distribution of the heat pipe micro reactor under a steady-state working condition. The method pre-constructs a high-fidelity fission response function database through a Monte Carlo method, does not need to repeatedly perform a complex particle transport process during operation, and only needs to complete neutronics solution through matrix multiplication, so that the simulation accuracy and the calculation efficiency are effectively balanced.

The application relates to the technical field of medical data processing, and discloses a macroscopic cross-section database construction method, a dose determination method, a device and equipment, which comprises the following steps: setting multiple boron concentration values for the tissue types corresponding to a human body model; selecting corresponding neutron source parameters for the tissue types and the multiple boron concentration values, wherein the neutron source parameters comprise energy range values; dividing the energy range values into multiple discrete neutron energy groups; performing particle transport simulation based on the selected neutron source parameters, jumping between different neutron energy groups in the simulation process, and obtaining neutron reaction rates and neutron fluxes of the tissue types under the multiple boron concentration values and the multiple neutron energy groups; and obtaining neutron macroscopic cross-section values of the tissue types under the multiple boron concentration values and the multiple neutron energy groups based on the neutron reaction rates and the neutron fluxes, and constructing a multi-group macroscopic cross-section database. The application can improve the calculation efficiency of the radiation dose and improve the adaptability to individual metabolic differences during dose calculation.

The invention discloses a method for simulating particle transport and related equipment, and relates to the technical field of radiotherapy, and the method comprises the steps: constructing an equivalent density model along a particle transport direction based on the structure parameters of an energy regulator combination, and building a matched boundary information table, the boundary information table at least records the position information of the downstream boundary of each energy regulator piece in the energy regulator combination, the equivalent water thickness accumulated from the incident end to the boundary, and the air gap length between the boundary and the upstream boundary of the next energy regulator piece; obtaining a particle current position and boundary information table; the medium area where the current free path of the particles is located is judged, and differential calculation is carried out on offset generated by movement of the particles in different areas according to the medium area until the particles pass through the energy regulator combination to be transported; according to the method, rapid and accurate judgment and differential offset calculation of the boundary are realized, so that the boundary processing complexity is remarkably reduced and the calculation efficiency is improved on the premise of ensuring the physical simulation precision when the particles pass through the energy regulator.

The invention provides a cyclotron electrostatic deflection plate beam loss heat source reconstruction method, and relates to the technical field of particle accelerator thermal analysis and multi-physics field coupling calculation, and the method comprises the steps: 1, configuring beam dynamics simulation parameters, multi-particle tracking is carried out under a three-dimensional field graph containing a central area electromagnetic field, a harmonic coil magnetic field and an electrostatic deflection electric field, and a particle loss list is generated; step 2, transferring the particle loss list into a beam source file of a Monte Carlo radiation transport program, configuring Monte Carlo parameters including a deflection plate material, a boundary, a particle type and an energy spectrum, executing particle transport simulation, and obtaining a three-dimensional energy deposition matrix on an electrostatic deflection plate element; according to the method, high-resolution heat source reconstruction is realized, the peak temperature rise calculation error of the deflection plate can be reduced, a temperature field solving result can be fed back to optimize the particle source, and a reliable basis is provided for thermal structure design and cooling optimization of the electrostatic deflection plate.

This invention belongs to the technical field of multi-scale particle transport simulation, and discloses a kinetic solution method and system for multi-scale particle transport simulation. The method includes: a particle kinetic model based on discrete velocity form; selecting discrete points in velocity space; calculating the distribution function along the direction of the discrete points in velocity space at the center of the grid according to a compact scheme; accumulating the contribution values ​​of the distribution function to macroscopic physical quantities; scanning the downstream grid sequentially based on the direction of the discrete points in velocity space; changing the discrete points in velocity space and repeating the operation until the contribution values ​​of the grid at all discrete points in velocity space are accumulated, and obtaining the final macroscopic physical quantities; outputting the calculation results of macroscopic physical quantities when the convergence condition is met. This invention discloses a kinetic solution method and system for multi-scale particle transport simulation that balances computational memory, accuracy, and efficiency, and is particularly suitable for multi-scale particle transport simulation with a large number of discrete points in velocity space and strong heterogeneity.

The application discloses a kind of based on flow pattern recognition's deep sea mining multiphase flow particle delivery prediction and regulation method, the method includes: by acquisition equipment periodic acquisition pressure in pipeline, flow, bubble or droplet volume fraction, solid particle volume fraction in different positions;According to pipe diameter and the gas-liquid ratio obtained by calculation, mixed flow velocity, call pre-built flow pattern division algorithm, distinguish bubble flow, slug flow, vortex, annular flow;Solve the gas-liquid discrete unit volume fraction of any diameter in different flow patterns;According to the gas-liquid discrete phase volume fraction, obtain the delivery speed of solid particles in multiphase flow;Whether the solid particle delivery speed obtained is judged to reach the best interval, according to the result control multiphase flow in pipeline flow pattern or gas-liquid ratio, to adjust the delivery speed of solid particles.The present application can improve the efficiency of seabed mineral exploitation, and avoid the dangerous flow pattern formed by unreasonable gas-liquid distribution ratio, efficiency and safety are taken into account.

The invention comprises a thermochemical energy storage unit for storing energy storage material and for thermally insulating heat sources and sinks. The thermochemical energy storage unit comprises a particle transport system (101), a device for pressure regulation (102), a device for air dehumidification (103) and at least one modular exchange chamber (104). The modular exchange chamber (104) comprises a storage volume (110) for storing energy storage material (150), a shaft (113) and a transition region (114), a particle inlet (120) and a particle outlet (121) for introducing and discharging energy storage material (150), a gas inlet (122) and a gas outlet (123) for introducing and discharging a gas mixture, a sensor for monitoring (111), and a vibration system (112). The modular exchange chamber (104) can be exchanged for a modular replacement exchange chamber (104A). The particle transport system (101) can distribute the energy storage material (150) to a plurality of different modular exchange chambers (104). The storage volume (110) can be separated into two separate regions (170A, 170B) by a flexible separating wall (115) or by a layer of separating particles.

The invention comprises a thermochemical energy storage unit for storing energy storage material and for thermally insulating heat sources and sinks. The thermochemical energy storage unit includes a particle transport system (101), a pressure regulation device (102), an air dehumidification device (103), and at least one modular exchange chamber (104). The modular exchange chamber (104) comprises a storage volume (110) for storing energy storage material (150), a shaft (113) and a transition area (114), a particle inlet (120) and a particle outlet (121) for introducing and removing energy storage material (150), a gas inlet (122) and a gas outlet (123) for introducing and removing a gas mixture, a monitoring sensor (111), and a vibration system (112). The modular exchange chamber (104) can be replaced by a modular exchange chamber (104A).The particle transport system (101) can distribute the energy storage material (150) to several different modular exchange chambers (104). The storage volume (110) can be divided into two separate areas (170A, 170B) by a flexible partition (115) or by a layer of separating particles.

Various embodiments of the present disclosure relate to methods and apparatus for fast impact matrix generation. These teachings are for fast and accurate formation of an impact matrix by generating the impact matrix via integration with Monte Carlo particle transport simulations. The resulting impact matrix can then be utilized in the ordinary way when optimizing a radiation therapy plan. By one approach, the foregoing includes generating an impact matrix via integration with Monte Carlo particle transport simulations on a particle-by-particle basis. For example, for each particle, these teachings can provide identifying the point to which the particle belongs, and then adding a dose deposited by the particle during transport to an impact matrix element corresponding to the point to which the particle belongs and the voxel in which the dose was deposited.

The present application is a pollution forecasting and tracing method based on Lagrangian particle transport, which is based on the source-receptor relationship (SRR) simulated by the FLEXPART model, combined with the station observation data to correct the emission inventory of pollutants by using the Bayesian optimization method. The real-time prediction of pollutants is carried out by using the corrected emission inventory, which can not only improve the real-time prediction accuracy of pollutants, but also obtain the contribution rate and spatial distribution of each type of pollution source (industry, power, residents and transportation), which can provide corresponding reference information for environmental management, public health protection and national and provincial scale emission reduction decision making.

The application discloses a casing-after-density inversion calculation method and device, equipment and a storage medium. According to the technical scheme provided by the application, the nuclear radiation particle transport process of the downhole gamma ray is simulated, a detector count ratio matrix is constructed, and a target function is constructed according to the detector count ratio matrix; the detector is used to detect the gamma ray of the casing well, and actual detection data of the detector is obtained; the actual detection data is substituted into the detector count ratio matrix to obtain a first count ratio function, and standard detection data under a standard condition is substituted into the detector count ratio matrix to obtain a second count ratio function; the target function is solved by using the first count ratio function and the second count ratio function, and the formation density and the cement density are determined. According to the application, the standard detection data and the actual detection data can be used to perform inversion based on the target function, and the formation density and the cement density can be accurately obtained.

The application provides a kind of proton accelerator hole penetration radiation shielding design method, including establishing the model of proton bombardment target nucleus, the dose rate distribution field in the secondary particle transport process is counted by virtual grid technology, simultaneously, using weight window generator obtains weight window lower limit parameter file;According to the dose field distribution, the weight window lower limit parameter and the source bias parameter are obtained, so that the dose rate at the hole position and the dose rate distribution based on the grid technology are obtained using the parameters, and the hole penetration radiation shielding design is carried out;The dose rate calculation for the outside of the penetration pipeline of strong electricity, weak electricity, heating, water supply and drainage, process system and equipment in the radiation shielding design of proton accelerator can be realized, the collaborative design of multiple penetrations is realized, the economy and efficiency of shielding design are improved, and the radiation shielding analysis and design of proton accelerator hole penetration are efficiently and reasonably completed.

This invention discloses a method for constructing a magnetron sputtering system, relating to the field of vacuum coating equipment design technology. The method includes: S1, parametric modeling to obtain the spatial potential distribution and working gas ionization characteristic distribution within the cavity, calculating the argon ion trajectory to determine the sputtering area on the target surface, and calculating the secondary electron trajectory for damage assessment; S2, calculating target particle transport and static film thickness distribution based on the sputtering area; S3, calculating the dynamic film thickness distribution and coating uniformity of the carrier plate based on the movement mode of the transport mechanism, and obtaining the coating efficiency based on deposition time and average film thickness; S4, comparing the coating efficiency, coating uniformity, and secondary electron damage assessment results with preset design indicators, iteratively optimizing until the indicators are met, and outputting the optimized design parameters of the magnetron sputtering system. This method solves the modeling and calculation convergence problem under strong coupling conditions of multi-physics fields, significantly reducing the debugging cost and structural redundancy after equipment manufacturing.

Disclosed in the present invention are a correction method and apparatus for an electron collision reaction rate, and a device and a medium. The method comprises: performing calculation on the basis of a Boltzmann equation corresponding to the electron distribution in a six-dimensional phase space, so as to obtain the electron energy distribution in the six-dimensional phase space, and then performing calculation on the basis of the electron energy distribution, so as to obtain electron collision reaction coefficients; on the basis of a preset Poisson equation and a preset particle transport equation, performing calculation to obtain the electric-field distribution and electron density in the six-dimensional phase space; on the basis of the electric-field distribution and the electron density, obtaining a corresponding electron energy transport equation, obtaining, on the basis of the electron energy transport equation, an electron energy loss balance in an inelastic collision process, and then obtaining a correction coefficient for an electron collision reaction rate; and on the basis of the correction coefficient for the electron collision reaction rate and the electron collision reaction coefficients, obtaining a corrected electron collision reaction rate. By means of the present invention, an electron collision reaction rate can be corrected.

The application relates to the technical field of particle deposition and semiconductor radiation resistance analysis, and discloses an alpha particle energy deposition calculation method based on a Monte Carlo particle transport simulation tool, which sequentially comprises material and particle source setting, use of an energy deposition scorer, statistics of single particle events, calculation of a soft error rate, and output and data analysis. By using the application, the need for field experiments is greatly reduced, and the time and cost required by experiments are saved. Moreover, by using a simulation method, a designer can more efficiently calculate the energy deposition of alpha particles in a semiconductor device and obtain the soft error rate of the alpha particles, and can perform radiation resistance reinforcement design of the semiconductor device according to the data, so that the radiation resistance performance and reliability of the device are improved.

The application discloses a multi-nucleus neutron nuclear reaction data verification method and device based on deep learning, comprising the following steps: determining a target nucleus to be evaluated, and obtaining multi-dimensional physical characteristic data of the target nucleus from a preset evaluation nuclear database and an experimental database; performing physical perception preprocessing and feature splicing on the multi-dimensional physical characteristic data to obtain a physical characteristic vector of the target nucleus; constructing and training a nuclear data correction model with uncertainty quantification capability; determining evaluation cross-section data and uncertainty data of the target nucleus according to the nuclear data correction model and the physical characteristic vector, and encapsulating the evaluation data of the target nucleus according to the evaluation cross-section data and the uncertainty data; verifying the evaluation data based on particle transport simulation, and optimizing the evaluation nuclear database according to the verified evaluation data. The application improves the efficiency and reliability of neutron nuclear reaction data evaluation and verification, and can be applied to the technical field of data processing.

A system (20) for detecting anomalies of a transmission assembly (8) of an aircraft (1). The aircraft (1) comprises a lubrication system (10), which comprises a tank (11) containing a lubricating fluid, a nozzle (12) configured to supply the lubricating fluid to the transmission assembly (8) and a fluid line (13), which fluidly connects the tank (11) to the nozzle (12). The detection system (20) comprises a first device (22), which detects a first quantity (n) associated with particles transported by the lubricating fluid along the fluid line (13), a second device (23), which detects a second quantity (ai) associated with vibrations of the transmission assembly (8) and an electronic control unit (24). The electronic control unit (24) verifies whether one between the first quantity (n) and the second quantity (ai) satisfies a first control criterion, whether the other between the first quantity (n) and the second quantity (ai) satisfies a second control criterion when the first control criterion is not satisfied and determines the presence of a possible anomaly of the transmission assembly (8) and / or provides for corrective actions when neither control criteria are satisfied.

The application discloses a kind of monte carlo fast dose calculation methods, load simulation parameter;Get the particle source phase space data of radiotherapy accelerator;Get human anatomy image data, and reconstruct adult three-dimensional matrix of body;Three-dimensional body matrix is gridded;Input monte carlo dose calculation parameter, construct fine monte carlo dose calculation physical model;The application utilizes the structured sparse characteristics of NVIDIAGPU, dynamically compresses input data, so that the effective utilization rate of video memory is improved, and the continuous operation of the computing task is ensured;MIG instance management technology combines multidimensional scheduling and cross-instance collaboration to improve GPU resource utilization, especially in the multi-task parallel scene. The two work together to fully utilize the hardware performance of NVIDIA Ampere and newer generation architecture GPU, improve the efficiency of Monte Carlo dose calculation to a new level, reduce the calculation time, and effectively support the GPU Monte Carlo calculation requirements of particle transport.

The present disclosure relates to a particle transport simulation method which includes obtaining a virtual particle source, simulating a deflection of the virtual particle source under a magnetic field to obtain a deflected particle, modeling one or more of a range modulator, a beam limiting hole, and an exit window based on physical properties of the range modulator, the beam limiting hole and the exit window, respectively, to obtain one or more of a range modulator model, a beam limiting hole model, and an exit window model, and simulating physical processes of the deflected particle in the one or more of the range modulator model, the beam limiting hole model, and the exit window model, respectively.

This invention discloses an X-ray shielding design method, system, device, and storage medium, relating to the field of radiation protection technology. The method includes the following steps: modeling multiple X-ray sources based on their actual locations and geometric structures using radiation particle transport software to obtain a computational model; determining the geometric structure of the shield to be designed based on the computational model; obtaining the material and dimensions of the shield to be designed based on a comparison of the simulated dose value of the target area when unshielded with a set dose limit; combining the geometric structure, material, and dimensions of the shield to be designed to obtain a shield model; integrating the shield model into the computational model to obtain a shielding computational model; and iteratively optimizing the shield model using the shielding computational model under the constraint of a set dose limit for the target area. This invention overcomes the shortcomings of traditional methods in handling the combined effects of multiple sources and spatial constraints, and is particularly suitable for shielding design in compact spaces.

The application relates to the technical field of radiotherapy, and particularly provides a Monte Carlo particle transport calculation method and system suitable for neutron therapy. The method comprises the following steps: acquiring a dose calculation input file; and acquiring irradiation dose by selecting one of a particle tracking algorithm and a particle weight attenuation algorithm based on preset conditions through a Monte Carlo program according to the input file.

The invention provides an aluminum alloy electron range estimation method, system and device and a storage medium, and relates to the technical field of space radiation protection, and the method comprises the steps: generating a particle transport calculation model of an aluminum alloy according to the component proportion and geometric characteristics corresponding to the aluminum alloy; according to the particle transport calculation model, through a Monte Carlo simulation method, obtaining original range data of electrons after interaction with the aluminum alloy through preset incident energy data; according to the range original data, the range-energy mapping relation of the aluminum alloy is obtained; determining a continuous estimation function through an interpolation algorithm according to the range-energy mapping relation; and outputting a real-time range estimation result of the target electron in the aluminum alloy through the continuous estimation function in combination with the real-time incident energy of the target electron. Based on the actual components and the geometric structure of the aluminum alloy, the estimation precision and efficiency of the electronic range in the aluminum alloy are improved by using the continuous estimation function.

The present invention relates to a waste treatment chamber (100) configured to operate in any one of a loading mode, a treatment mode, and an unloading mode, further configured to provide an inside environment of the treatment chamber (100) in the treatment mode for particle disinfection of medical waste using ozone, the treatment chamber comprising an inlet (110) configured to receive particles of medical waste in the loading mode, and configured to provide a gas-tight seal between the inside environment and an outside environment of the treatment chamber (100) in the treatment mode and the unloading mode, an outlet (120) configured to remove particles of medical waste from the treatment chamber (100) in the unloading mode, and configured to provide a gas-tight seal between the inside environment and the outside environment of the treatment chamber (100) in the loading mode and the treatment mode, a particle transport arrangement (130) configured to agitate particles of medical waste in the loading mode and the treatment mode, and further configured to move particles of medical waste to the outlet (120) for removal in the unloading mode, one or more sensors (S1, S2) configured to measure a characteristic of the sealed environment inside the treatment chamber (100), the treatment chamber fluidically coupled to or comprising a generator (G) configured to generate ozone and to maintain a target concentration level of ozone of the inside environment of the treatment chamber (100).

This invention discloses a pellet transport device, comprising a pellet lifting mechanism and a transverse pellet transport mechanism located at the upper and lower ends of the pellet lifting mechanism; the transverse pellet transport mechanism includes: a movable guide rail; a transport vehicle movable along the movable guide rail; a transverse drive assembly operably connected to the transport vehicle to drive the transport vehicle to move along the movable guide rail; a pellet tank connected to the transport vehicle, the upper end of the pellet tank having a feed inlet and a feed locking mechanism operably opening or closing the feed inlet, and the lower end of the pellet tank having a discharge outlet and a discharge locking mechanism operably opening or closing the discharge outlet; and an opening / closing assembly operably connected to the feed locking mechanism or the discharge locking mechanism to open or close the feed locking mechanism or the discharge locking mechanism. The pellet transport device provided by this invention eliminates the need to rotate the pellet tank when transferring pellets from the lower storage tank to the pellet tank or transferring pellets from the pellet tank to the upper storage tank.