11 results about "Plasma parameters" patented technology

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

This invention belongs to the field of photon counting detector manufacturing technology, specifically relating to a plasma treatment method for the crystal surface of a photon counting detector and the resulting photon counting detector. The treatment method employs a step-by-step plasma surface modification process. First, the crystal wafer surface is bombarded with plasma generated by the ionization of an inert gas. Then, a secondary bombardment is performed using plasma generated by the ionization of reactive gases such as oxygen and hydrogen. Simultaneously, key process conditions such as process gas flow rate, wafer orientation bias, processing time, cavity vacuum, radio frequency power, plasma parameters, and wafer spacing are systematically controlled. This step-by-step modification process achieves nanoscale modification of the crystal surface, effectively repairing surface damage caused by processing and forming a uniformly distributed surface modification layer. Photon counting detectors fabricated using this method can significantly reduce device leakage current, improve withstand voltage performance, optimize energy resolution, and improve photon counting rate and counting stability.

This invention discloses a Langmuir probe fixing assembly for a vacuum chamber, relating to the field of nuclear fusion device technology. The probe fixing assembly includes a probe array disk and an insulating mounting structure. An array aperture platform is provided in the center of the probe array disk, and the array aperture platform is used to pass through corresponding probe array needles. One end face of the probe array disk is detachably connected to one end of the insulating mounting structure, and the other end of the insulating mounting structure is used to be fixedly connected to the inner wall of the vacuum chamber. This allows for changes in the layout of the probe array according to different experimental requirements, reducing the workload and economic cost of replacing the entire probe, and improving the probe's ability to measure plasma parameters. A plasma measurement assembly includes a probe array box and the aforementioned Langmuir probe fixing assembly for a vacuum chamber. One end of the probe array box is provided with probe array needles, and the end of the probe array box with the probe array needles is fixedly connected to the probe array disk.

The invention discloses a Tokamak device plasma discharge starting method and system, and relates to the technical field of magnetic confinement fusion. The method comprises the following steps: generating initial plasma through the plasma pre-ionization system; the neutral beam injection system injects neutral particles into the initial plasma, and the injection energy is dynamically adjusted according to the plasma density monitored in real time; the electron cyclotron wave heating system injects microwave energy to drive electrons to generate plasma current; the diagnosis system monitors plasma parameters and neutral beam penetration depth in real time, and feeds back the parameters to the injection system and the heating system to adjust the parameters; and after the plasma current reaches the standard and is stable, parameters are optimized to maintain steady-state operation. The system comprises a pre-ionization module, an injection module, a heating module, a diagnosis module and a control module. According to the invention, the volt-second consumption and construction cost are reduced, the starting efficiency and stability are improved, the device is prevented from being damaged, and various magnetic confinement fusion devices are adapted.

The invention discloses a light, heat and cold plasma concerted catalytic reaction device which comprises a gas treatment unit, a cold plasma generation unit, a reaction unit and a control unit, and the gas treatment unit is responsible for gas pretreatment and product separation; the cold plasma generation unit generates dielectric barrier discharge plasma to activate reactants; the reaction unit integrates plasma generation, wide-range temperature control and illumination structures, and can be compatible with flat plate type and tubular reactors suitable for different temperature zones (300-800 DEG C); the control unit performs centralized programming through upper computer software and accurately regulates and controls gas flow, temperature, plasma parameters and illumination conditions, and the device can flexibly combine light, heat and cold plasma energy fields, supports multiple reaction modes such as segmented pre-activation and integrated cooperation, and is suitable for large-scale industrial production. The problems that existing equipment is single in function, limited in working temperature interval and low in intelligent degree are solved, and a standardized platform is provided for multi-field coupling catalysis research.

The present application relates to the technical field of plasma analysis, and discloses a dust plasma parameter inversion method, which comprises the following steps: firstly, measuring the attenuation coefficient of dust plasma to microwaves through experimental measurement; secondly, inversely deducing the dielectric coefficient and conductivity of dust plasma from the attenuation coefficient calculation formula; thirdly, substituting the deduced result into the dust plasma dielectric coefficient and conductivity calculation formula to obtain the electron concentration, dust particle concentration and dust particle radius in the dust plasma; and finally, verifying the reliability of the inversion result. The present application is based on the microwave transmission theory and experimental research of dust plasma, verifies and perfects the related theory, and proposes a measurement method of internal parameters of dust plasma, which has practical significance for further exploring the radio physics problems in dust plasma.

The invention discloses a simulation modeling method and device for a trigger breakdown process of a surface flashover type trigger vacuum switch, electronic equipment and a storage medium. The method comprises the following steps: determining a trigger condition of the surface flashover type trigger vacuum switch; according to the trigger condition, performing simulation calculation on the trigger breakdown process of the surface flashover type trigger vacuum switch to obtain the surface discharge characteristic of the surface flashover type trigger vacuum switch; according to the electron current density of the local surface of the anode, performing simulation calculation on the evaporation process of the local surface of the anode in the surface flashover type trigger vacuum switch to obtain the evaporation characteristic of the local surface of the anode under the action of the electron current; according to the evaporation characteristic and the density of the initial electrons diffused into the main gap, performing simulation calculation on the main gap breakdown process of the surface flashover type trigger vacuum switch so as to obtain an evolution rule of microscopic plasma parameters of the surface flashover type trigger vacuum switch; and multi-physics field coupling simulation of the trigger breakdown process of the surface flashover type trigger vacuum switch is realized.

The invention discloses a plasma constrained mode conversion control method based on boundary particle injection assistance, and relates to the technical field of constrained mode conversion control, and the method comprises the steps: calculating an initial set value of a power threshold through a built-in prediction model of a control unit based on the operation parameters of a current plasma, and entering a closed-loop control stage; in the closed-loop control stage, real-time plasma parameters are obtained through a diagnosis module; calculating a real-time power threshold value based on the plasma parameters, and comparing the real-time power threshold value with an initial set value to obtain a comparison result; according to a comparison result, dynamically adjusting injection parameters of a neutral particle injection module for injecting neutral particles into the plasma boundary region and heating power of a heating module for injecting energy into the plasma through a control unit in different control modes; the problems of high power dependence, inaccurate control and unstable conversion in the prior art are solved, and efficient and adaptive L-H conversion is realized.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

The application provides a method, device and medium for evaluating ion cyclotron resonance heating efficiency of a stellarator. The method comprises the following steps: obtaining plasma parameters of plasma in the stellarator, wave parameters of incident waves used for heating the plasma, and device parameters of the stellarator, calculating single-pass absorption parameters used for evaluating the heating efficiency according to the plasma parameters, the wave parameters and the device parameters, and determining a heating type of ion cyclotron resonance heating according to ion properties of the plasma in the stellarator; determining a single-pass absorption model corresponding to the heating type, and calculating a single-pass absorption rate corresponding to the heating type by using the single-pass absorption model according to the single-pass absorption parameters, the wave parameters and the device parameters; and evaluating the heating efficiency according to the single-pass absorption rate. The heating efficiency evaluation method provided by the application is suitable for a single machine environment, does not consume too much computing power, and has a small error.

The invention discloses a high-power negative ion source multichannel current filtering magnetic field method, which belongs to the technical field of nuclear fusion neutral beam injection, and comprises the following steps: designing and optimizing a plasma electrode of a high-power negative ion source multichannel current filtering magnetic field device: forming a resistance balance groove in one surface, facing an extraction electrode, of the plasma electrode; designing an independent cooling water path: separating the plasma electrode from a cooling water inlet pipeline and a cooling water return pipeline of other parts, and arranging an independent flow meter and a temperature sensor; and debugging a power supply function and a current control function of a filtering magnetic field power supply of the high-power negative ion source multi-channel current filtering magnetic field device to obtain an optimal filtering magnetic field current parameter under different plasma parameter conditions so as to guide a long pulse operation experiment. According to the invention, a more uniform and stronger filtering magnetic field can be generated, and the electron temperature of the area near the leading-out surface of the high-power negative ion source is effectively reduced.