14 results about "Neutral particle" patented technology

The invention relates to a method and a device for reducing a local thermal load on a surface of a particle collection device that is struck by electrically charged particles. The electrically charged particles may correspond in particular to a fraction of non-neutralised ions from a particle beam of neutralised ions downstream of a neutraliser of a neutral beam injection device of a fusion reactor. The method comprises changing, preferably continuously, the point of impact (P) of the charged particles (8) on the surface (34) by exposing the charged particles (8) to at least one magnetic and / or electric field, the field lines of which are oblique or perpendicular to a flight direction of the charged particles and the field strength of which is varied, preferably continuously, in order to change the point of impact (P) so as to reduce a local thermal load on the surface (34), the surface (34) being designed as an area with an open cross-section.

The application discloses an integrated high-energy particle detector for a magnetic confinement fusion device, mainly comprising a cross collimator and a scintillator plate, front, rear, upper and lower collimating holes are formed in the cross collimator, the upper and lower collimating holes are arranged in a cross shape with the front and rear collimating holes, and an electron stripping film is installed on the top of the upper collimating hole. Ions with different energies and pitch angles pass through the front and rear collimating holes, thereby hitting different coordinates on the scintillator to emit scintillation light; for high-energy neutral particles without electricity, the high-energy neutral particles pass through the lower collimating hole and the upper collimating hole in sequence, then pass through the electron stripping film to be stripped of electrons to become ions, and then make Larmor cyclotron motion in a magnetic field and hit the scintillator to emit scintillation light, therefore, the integrated high-energy particle detector can simultaneously detect high-energy ions and high-energy neutral particles in the magnetic confinement fusion device.

The invention discloses an E / / B neutral particle analyzer detector for a Tokamak device, which belongs to the technical field of high-temperature plasma diagnosis and comprises a magnet structure for generating a specific magnetic field structure and a vacuum chamber structure for passage of charged ions. The electrode plate structures are used for guiding the charged ions to deflect; the detector main body structure is used for receiving the charged ions; the magnet structure is vertically fixed on a plane, the vacuum chamber structure is fixed and tightly attached in a gap of the magnet structure, the electrode plate structure is fixed in the vacuum chamber structure, and the detector main body structure is fixed in the vacuum chamber structure. While the target magnetic field structure and the energy detection range are met, the overall size and mass of the device are effectively optimized.

A plasma source having an adjustable exit aperture is disclosed. The plasma source has a cylindrical body and two ends, wherein a housing aperture is formed along the cylindrical body. An adjustable output plate is disposed on the cylindrical body and covers the housing aperture. The adjustable output plate has an exit aperture, smaller than the housing aperture. The adjustable output plate is capable of rotation in the circumferential direction, thus moving the position of the exit aperture relative to a workpiece holder. The plasma source is configured such that changes to the exit angle may be performed without breaking vacuum. In some embodiments, a defining aperture is located outside the exit aperture to define the path of radicals and neutrals. In other embodiments, biased electrodes may be disposed outside the exit aperture.

A plasma source having an adjustable outlet opening is disclosed. The plasma source has a cylindrical body and two ends, with a housing opening formed along the cylindrical body. An adjustable output plate is positioned on the cylindrical body and covers the housing opening. The adjustable output plate has an outlet opening smaller than the housing opening. The adjustable output plate is circumferentially rotatable and thus moves the position of the outlet opening relative to the workpiece holder. The plasma source is configured such that changes in the outlet angle can be performed without breaking the vacuum. In some embodiments, a delimiting opening is positioned outside the outlet opening to define the paths of radicals and neutral particles. In other embodiments, a biased electrode may be positioned outside the outlet opening.

The invention discloses a method and system for optimizing two-dimensional argon plasma uniformity by introducing a high-energy particle source, and the method comprises the steps: S1, filling a plasma reaction chamber with background gas, and simulating the distribution of neutral particles; s2, initializing the speed and the position of charged particles in the gas in the chamber, enabling the charged particles to be uniformly distributed in the chamber, and determining the intensity, the time sequence, the incident direction and the incident position of high-energy particles emitted by an external particle source; s3, calculation of charged particle density, potential and electric field; s4, calculating the force acting on the charged particles; s5, moving the charged particles; s6, checking and executing collision; and S7, repeating the steps S3 to S6, adjusting the high-energy particle injection time sequence until a steady state is reached, and obtaining the data distribution of the charged particles. Through controllable interaction between an external particle source and plasma or background gas, seed electrons-ions are actively generated in a specific space area or energy distribution is changed, and inherent space non-uniformity of the plasma is compensated.

The embodiment of the invention discloses a high-pressure gas switch arc plasma particle component prediction method, system, medium and equipment, and the method comprises the steps: constructing a thermochemical database, and storing the thermodynamic parameters of SF6, air, fluorocarbon and dissociation / ionization decomposition products thereof, and metal steam; the method comprises the following steps: performing atomic-scale decomposition on a detected arc extinguishing medium to identify basic elements, extracting metal vapor, neutral particles containing the elements and charged ions generated by ionization of the neutral particles in combination with a database, and forming a candidate particle list; constructing a reaction equation library (reactants and products are from candidate lists) on the basis of mass conservation, and determining dominant reaction paths under different temperatures and pressures; determining particle number density distribution during balance according to the dominant path, constructing a neural network model taking temperature pressure as input and number density as output, defining a loss function and completing training; and finally, inputting the current arc temperature pressure to quickly obtain the corresponding population density distribution so as to provide support for the optimization of the arc extinguishing performance of the high-voltage switch.

The invention provides a magnetic shielding structure for a detector in a neutral particle analyzer of a Tokamak device, which belongs to the technical field of nuclear fusion diagnosis and comprises a common magnetic shielding cover body, an independent magnetic shielding cover body and a grid shaped like a Chinese character'jing 'on a signal input window at the front end of the independent magnetic shielding cover body. Compared with a traditional design of adding an independent magnetic shielding cover body to a common magnetic shielding cover body, a #-shaped grating framework is additionally arranged on a signal input window at the front end of the independent magnetic shielding cover body, a low-carbon steel material is adopted, and the grating divides an open area into nine independent magnetic compensation areas under the condition that the functions of the detector are not influenced, so that the performance of the detector is improved. And the magnetic field can be reduced to be less than 25Gs that the PMT detector can normally work. According to the invention, the problem of signal distortion of the photomultiplier (PMT) caused by high-intensity magnetic field interference is solved, and a stable and efficient magnetic shielding mode is provided.

The present invention appropriately controls the distribution of charged particles in an ion source. To this end, the present invention comprises: a plurality of plasma generation units (140) each provided with a magnetic flux generation unit (143); an expansion chamber (160) that is connected to the plurality of plasma generation units and emits charged particles; and a magnetic path member (150) through which the magnetic flux generated by the magnetic flux generation units passes. Defining a first magnetic flux density (B) to be the magnetic flux density in an interior space of the expansion chamber and defining a second magnetic flux density (B0) to be the magnetic flux density in the interior space of the expansion chamber in the case of having removed the magnetic path member, the magnetic path member is formed such that the magnetic flux density ratio (B / B0) at a central axis (CL-P) of the expansion chamber and the magnetic flux density ratio (B / B0) at the periphery of the expansion chamber are different.

The application discloses a simulation method for tokamak neutral beam injection and fast ion deposition. In the numerical simulation of the neutral beam particle injection and ionization process in a tokamak device, the physical parameters of the neutral beam injection device are determined first, then the injection source is simplified by using a narrow particle beam model, the neutral beam particle density of a reference point given under geometric conditions is calculated, the average free path of the neutral beam particle ionization is calculated after the parameters of the position of the reference point in the plasma interior are obtained, the ions in different regions are divided by using a non-uniform grid and are given different weights, and finally the simulation process of the neutral beam injection is realized. The application realizes the simulation of the injection process of the neutral beam particles by using the narrow particle beam model, can obtain the neutral particle and fast ion distribution at any position in the plasma, has high calculation efficiency and strong numerical stability, and is a stable and efficient numerical simulation method.

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.

In the ion source, the distribution of charged particles is appropriately controlled. [Solution] The system comprises a plurality of plasma generation units 140, each having a magnetic flux generating unit 143; an expansion chamber 160 connected to the plurality of plasma generation units 140 and emitting charged particles; and a magnetic path member 150 through which the magnetic flux generated by the magnetic flux generating units 143 passes. The magnetic flux density in the internal space of the expansion chamber 160 is defined as a first magnetic flux density B, and the magnetic flux density in the internal space of the expansion chamber 160 when the magnetic path member 150 is removed is defined as a second magnetic flux density B0. The magnetic path member 150 is formed such that the magnetic flux density ratio B / B0 at the central axis CL-P of the expansion chamber 160 is different from the magnetic flux density ratio B / B0 at the peripheral edge of the expansion chamber 160.

A plasma treatment system solves the problem of providing independent control over ion and neutral particle fluxes by separating the workpiece from the plasma and placing the workpiece on a movable stage. Extraction electrodes are used to extract ions from the plasma and beam them at the workpiece. The neutral particles are allowed to project from the plasma to the workpiece. The neutral particle flux has a much stronger dependence on distance from the plasma source than the ion flux. Accordingly, the neutral particle to ion flux ratio may be adjusted by moving the stage toward or away from the plasma source. This system has the additional advantage of enabling directional processing wherein the workpiece is held at a tilt with respect to the ion beam as the workpiece is scanned through the ion beam.

This invention relates to a method and system for measuring the total deposition rate of impurities in the magnetic shadow region of a tokamak. First, the neutral particle energy spectrum and net corrosion or deposition rate of the material in the magnetic shadow region are measured using a low-energy neutral particle analyzer and a quartz crystal microbalance. Second, based on the measurement results from the quartz crystal microbalance, the total corrosion rate of the material by neutral particles is calculated by selecting the corresponding sputtering yield and combining it with the neutral particle energy spectrum and solid angle. Then, the conversion factor for the corresponding net corrosion or deposition rate is determined. Finally, based on the theory that the corrosion and deposition results in the magnetic shadow region of a tokamak device are determined by the competition between neutral particle corrosion and impurity deposition, the total deposition rate of impurities is obtained. This invention can accurately measure the total deposition rate of impurities in the magnetic shadow region of a tokamak in situ and in real time, helping to understand the physical mechanism of impurity deposition and providing support for the safe operation of future fusion reactors.