13 results about "Plasma current" patented technology

A plasma power supply (10) and a control method therefor, and a fusion reaction system. The plasma power supply (10) comprises: a breakdown power supply module (101) and an extraction power supply module (102). The breakdown power supply module (101) is used for: outputting a first voltage to a plasma generator (20) which generates plasma under the application of the first voltage; and when the output voltage is decreased from the first voltage to a second voltage, maintaining the output of the second voltage to the plasma generator (20). The extraction power supply module (102) is used for forming an electric field between the plasma generator (20) and a housing (30) of a nuclear fusion reaction chamber, and when the plasma generator (20) generates the plasma, forming a plasma current between the housing (30) and the plasma generator (20) on the basis of the plasma and the electric field. The plasma power supply (10) allows for direct formation of the plasma current in the nuclear fusion reaction chamber, thereby simplifying the formation process of the plasma current.

The invention discloses an underwater plasma arc cutting device for a large-diameter seamless steel pipe. The underwater plasma arc cutting device comprises a water tank, a displacement system, a multi-degree-of-freedom manipulator, a plasma arc cutting system and a visual sensing and control system. A pressure sensor, a temperature sensor, a hydrogen concentration sensor and a carbon monoxide concentration sensor are arranged in the water tank. A supporting rotating mechanism is arranged in the water tank and used for clamping and driving the large-diameter seamless steel pipe to rotate around the axis of the large-diameter seamless steel pipe. The displacement system is arranged on one side of the water tank, and the multi-degree-of-freedom mechanical arm is installed on the displacement system. A cutting torch of the plasma arc cutting system is installed at the output end of the multi-degree-of-freedom mechanical arm and used for extending into the water tank to cut the steel pipe. And the visual sensing and control system is used for monitoring the cutting process in real time and controlling the plasma arc cutting system, the multi-degree-of-freedom manipulator and the supporting and rotating mechanism to move. Parameters such as the cutting torch position, the cutting track, the plasma current, the gas flow and the cutting speed can be dynamically adjusted through the visual sensing and control system.

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 application discloses a kind of spherical tokamak's equilibrium field power supply, equilibrium power supply method, comprising: constant current source I3 with equilibrium field coil electric connection;Two groups of capacitor banks are respectively connected with equilibrium field coil, for supplying equilibrium field coil a steady-state low-level or high-level current balance high plasma current;Two groups of charge-discharge circuits are respectively connected with two groups of capacitor banks.Based on the equilibrium field power supply of spherical tokamak, the equilibrium power supply method of two groups of capacitors is used to supply power to the equilibrium field coil, so that the low plasma current is balanced by the equilibrium field current provided by constant current source I3, and the high plasma current is balanced by the equilibrium field current provided by two groups of capacitor banks.In the presence of low plasma current, ohmic field is put in, and plasma current is improved to a certain extent.In this way, the problems of limited volt-second product of spherical tokamak ohmic transformer, insufficient coil installation precision and stray field influence caused by vacuum wall eddy current can be compensated.

The application provides a method for preparing single-walled carbon nanotubes by a plasma-assisted chemical vapor deposition method, and relates to the technical field of nanometer material preparation. The method adds controllable plasma current and voltage to the condition of chemical vapor deposition. The plasma promotes the polymerization and growth of carbon atoms by providing a high-energy field and a catalyst activation effect. In the chemical vapor deposition method, iron sulfate and an iron-containing inorganic compound are used in combination. The addition of sulfur can promote the crystallization and arrangement of carbon atoms, and the combination of the two can reduce the surface defects of single-walled carbon nanotubes and reduce the use cost. The method for preparing single-walled carbon nanotubes by the plasma-assisted chemical vapor deposition method can prepare single-walled carbon nanotubes with a Raman G / D ratio of more than 120 while reducing the cost, and large-scale production is realized.

The invention discloses an online quality monitoring system for high-strength steel laser-plasma composite cutting, which belongs to the field of composite cutting online quality monitoring and comprises a data acquisition module, a splash characteristic threshold judgment module, a real-time path comparison module, a process curve comparison module and a bimodal factor diagnosis module. The invention discloses an on-line quality monitoring system for high-strength steel laser-plasma composite cutting, which is characterized in that a data acquisition module acquires laser power, plasma current and other process parameters in real time, and synchronously captures an original image of a cutting area through a three-channel camera; the spatter characteristic threshold determination module establishes a parameter-spatter mapping library and outputs a parameterized threshold; the real-time path comparison module is used for stripping the splashing point and comparing a preset path; the process curve comparison module judges a process abnormal point through the reference arc line; the bimodal factor diagnosis module outputs a quality problem judgment result, real-time monitoring and accurate quality diagnosis in the cutting process are achieved, and it is guaranteed that the cutting quality is stable.

The present application relates to the technical field of controllable nuclear fusion, and particularly relates to a device for controlling energy confinement time by using a limiter bias system. The device comprises a bias electrode head, a soft connection wire connected with the bias electrode head at one end and connected with a bias power supply system of an NCST spherical tokamak device at the other end, and a limiter main body installed on one side of the NCST spherical tokamak device and provided with the bias electrode head for restraining the escaped electrons generated by discharge of the NCST spherical tokamak device. The present application can restrain the escaped electrons generated by discharge of the NCST spherical tokamak device by installing the limiter bias system, improve the energy confinement time parameter of the NCST spherical tokamak device, significantly restrain the plasma instability, and thus increase the plasma current duration and improve the plasma current size.

The application belongs to the technical field of nuclear fusion, and discloses a tokamak plasma vertical displacement event disruption prediction method based on a random forest. The technical scheme comprises the following method steps: S1, obtaining tokamak plasma equilibrium parameters, shape control data and plasma current control data, and cleaning the data; S2, setting different segmentation points according to whether each parameter of each discharge gun is stable or not, and marking them as 0 and 1 respectively; S3, verifying whether each gun has separability by using a t-SNE algorithm. The application inputs different plasma parameters in the tokamak into a machine learning model, sets a threshold value for judgment, and outputs an early warning signal. The method of artificial intelligence is introduced into the EAST tokamak plasma vertical displacement disruption prediction, and the problem of low accuracy of the disruption prediction is solved.

This invention relates to the interdisciplinary field of quantum computing and nuclear fusion plasma profile reconstruction, and particularly to a tokamak plasma current density reconstruction system based on a coherent Ising machine. The technical solution includes an electromagnetic diagnostic data acquisition unit and a Bayesian posterior modeling processor. The electromagnetic diagnostic data acquisition unit is used to acquire external electromagnetic measurement data of the tokamak device in real time, forming a measurement vector. The Bayesian posterior modeling processor is connected to the electromagnetic diagnostic data acquisition unit and is used to construct a posterior accuracy matrix and a linear term coefficient vector based on a conditional autoregressive prior model and the electromagnetic measurement likelihood probability. This invention organically integrates Bayesian inference modeling, spatial block decomposition, block coordinate descent iterative control, and coherent Ising machine quantum solving, achieving high-precision, rapid reconstruction of the tokamak plasma current density profile with uncertainty quantification within the constraints of existing quantum hardware bit capacity.

A system for a thermonuclear fusion reactor having a feeder configured to introduce a fuel projectile into a contained plasma is described. The system includes one or more lasers for adjusting a propulsion force of the fuel projectile by laser ablation and a controller configured to operate in conjunction with the feeder and the one or more lasers to controllably propel the fuel projectile toward a target location in the contained plasma. This contrasts with existing systems (e.g., fuel projectiles simply follow the magnetic field gradient of the plasma), and may enhance plasma control to achieve improved stability and generation of thermonuclear fusion energy, modulate the fusion rate and the amount of energy generated by the reactor, and improve the performance of the reactor. Plasma current is adjusted to alter the magnetic field and generate electrical power by magnetic induction, and / or have other advantages alone or in combination with existing systems.

Disclosed herein are systems and methods for delivering nitric oxide gas. According to an embodiment, a nitric oxide gas delivery system can include: a first nitric oxide (NO) gas generator, wherein the first NO gas generator includes a plasma chamber enclosing two electrodes separated by a gap; a plurality of port lights surrounding a plurality of corresponding gas outlet ports, wherein each of the port lights are configured to display a color; and an electronic control circuit, wherein the electronic control circuit is configured to enable the plurality of port lights to display the color based on a status of a plasma current across the two electrodes.

The invention relates to the technical field of plasma energy engineering, and discloses a multi-pole magnetic trap magnetic flux distribution prediction method, device and equipment, and the method comprises the steps: constructing a neural network architecture comprising a magnetic flux neural network, a plasma current neural network and a convolution differential operator, and outputting total magnetic flux distribution through the magnetic flux neural network, the plasma current neural network is utilized to obtain the plasma current density from the total magnetic flux distribution and obtain a first constraint condition, meanwhile, a convolution differential operator is combined to obtain a second constraint condition from the total magnetic flux distribution, and a prediction result is determined by comparing convergence errors of the two constraint conditions. Physical constraints are introduced through a convolution differential operator, the problem of large deviation between magnetic flux distribution prediction and reality caused by lack of physical constraints of a common neural network is solved, and meanwhile, through feedback coupling between the magnetic flux neural network and the plasma current neural network, the convergence and stability of the model are improved, and the prediction precision is improved. And the method is closer to the actual multi-pole magnetic trap magnetic flux distribution prediction effect.

The invention belongs to the field of magnetic confinement nuclear fusion, and discloses a cladding integrated conductive loop system for a fusion reactor and a control method thereof.The system is integrated in a cladding area of a Tokamak device, cladding blocks are electrically connected to form a closed conductive loop, and under the condition that an independent excitation power source is not needed, the fusion reactor can be electrically connected with the closed conductive loop. The system enables a conductive loop to generate induced current in the rapid change process of plasma current, and comprises a vacuum chamber, plasma, cladding blocks and conductive connection blocks arranged between the adjacent cladding blocks. According to the integrated passive coil system and the control method, a non-axisymmetric disturbed magnetic field can be effectively excited during plasma rupture through cladding integrated design and reliable external switch control, efficient suppression of escape electrons is realized, and the reliability of the system is improved. And an effective technical scheme is provided for passive inhibition of escaped electrons of the reactor-grade Tokamak device.