Suspension dipole field plasma device

Abstract

The invention discloses a suspension dipole field plasma device which comprises a closed cabin, an induction charging coil, a suspension superconducting coil, a height adjusting assembly and a magnetic suspension supporting coil. A vacuum chamber is arranged in the closed cabin, and the bottom of the closed cabin extends downwards to form a cylindrical mounting cavity; the induction charging coil is arranged on the inner side of the cylindrical mounting cavity; the suspension superconducting coil is arranged on the inner side of the induction charging coil; the height adjusting assembly is arranged in the vacuum chamber, and the lifting end of the height adjusting assembly is connected with the suspension superconducting coil; the magnetic suspension supporting coil is arranged at the top of the closed cabin; according to the invention, a new way of realizing controlled nuclear fusion by adopting dipole magnetic field constraint is adopted, a traditional tokamak complex toroidal field coil system is replaced, no driving current is used, dipole field constraint is utilized to stabilize plasma, instability of magnetic fluids such as a tearing mode and a stripping mode is inhibited, thermal load of a first wall is reduced, the structure is simplified, and the energy efficiency is improved; and a low-cost and reliable new path is provided for realizing high-Q-value controlled nuclear fusion.

Description

Technical Field

[0001] This invention relates to the field of nuclear science and technology applications in thermonuclear fusion reactions, specifically a suspended dipole field plasma device. Background Technology

[0002] Nuclear fusion, as an important direction for future clean energy, is mainly represented by tokamak magnetic confinement fusion devices. It adopts magnetic confinement or inertial confinement as the core route and relies on plasma current to drive the confinement configuration. The device needs to operate in an ultra-high vacuum environment. It uses neutral beam injection, radio frequency heating and other methods to raise the plasma temperature to the order of hundreds of millions of degrees. It also uses first wall materials and divertors to deal with high heat load and particle ash removal problems. Magnetic confinement nuclear fusion devices typically maintain high-temperature plasma above 100 million degrees for tens of seconds during operation. Superconducting magnets generate a strong magnetic field of 5 Tesla to 10 Tesla to confine the plasma. Since the nuclear fusion reaction is mainly a DT (deuterium-tritium) reaction, the deuterium-tritium fuel can be extracted from seawater, which has the advantage of easy fuel acquisition. Moreover, it only produces inert helium gas and has no long-lived radioactive waste, thus also having the advantage of cleanliness.

[0003] The current engineering progress of magnetic confinement fusion devices is as follows: the International Thermonuclear Experimental Reactor (ITER) project has verified the feasibility of magnetic confinement, and Toco 3 has achieved a breakthrough in energy output. Although current magnetic confinement fusion devices possess the strategic advantages of unlimited fuel and clean, safe operation, they still face a series of critical scientific and engineering challenges on the road to commercial application. These key issues severely restrict their stability, economic viability, and sustainability.

[0004] First, magnetic confinement fusion devices employ a complex toroidal field coil system containing dozens of superconducting coils, such as poloidal field coils, central solenoid coils, and toroidal field coils, resulting in high economic and technological development costs. Second, magnetic confinement fusion devices rely on plasma current to achieve confinement configuration. Current is essential for maintaining plasma confinement; however, current-driven processes themselves are unstable, leading to plasma instability and a tendency to trigger boundary local modes and large-scale disruption events, resulting in instantaneous energy release and damage to the device. Third, the 14 MeV neutron irradiation damage from deuterium-tritium reactions in the DT (deuterium-tritium) reaction, along with the high thermal load from the plasma, causes the annual loss rate of the first wall material of the magnetic confinement fusion device to exceed 10%, and the amount of tritium retained on the tungsten layer surface of the first wall to exceed the safety limit by three times. Fourth, the plasma is located inside the superconducting magnet, leading to heat concentration, difficulty in ash removal, and the superconducting magnet's susceptibility to radiation, making it difficult for the overall energy gain Q value to exceed the commercial threshold. Summary of the Invention

[0005] The purpose of this invention is to provide a suspended dipole field plasma device to solve the problems of existing Carmak magnetic confinement fusion devices, such as complex structure, poor plasma stability, severe damage to the first wall material from high-energy neutron irradiation, and low net energy gain.

[0006] The technical solution of this invention is: A suspended dipole field plasma device includes a sealed chamber, an induction charging coil, a suspended superconducting coil, a height adjustment component, and a magnetic levitation support coil. The sealed chamber contains a vacuum chamber, and its bottom extends downwards to form a cylindrical mounting chamber. The sealed chamber has an inflation port for connecting to an external gas supply device. The induction charging coil is located inside the cylindrical mounting chamber. The suspended superconducting coil is located inside the induction charging coil. The height adjustment component is located inside the vacuum chamber and has a lifting end connected to the suspended superconducting coil. This lifting end is used to adjust the height of the suspended superconducting coil after charging it through the induction charging coil. The magnetic levitation support coil is located at the top of the sealed chamber and is used to magnetically position the suspended superconducting coil, which is adjusted by the height adjustment component, so that the suspended superconducting coil is suspended in the vacuum chamber. The dipole confinement magnetic field generated by the suspended superconducting coil confines the plasma generated by the discharge gas injected through the inflation port, placing the plasma outside the suspended superconducting coil.

[0007] Preferably, as a further improvement of the present invention, the height adjustment assembly includes a mounting rod, a first tray, a second tray, and a lifting mechanism. The mounting rod is vertically inserted through the center of the inductive charging coil, the levitation superconducting coil, and the magnetic levitation support coil. The lower end of the mounting rod is fixed to the inner bottom surface of the cylindrical mounting chamber. The first tray is fixed on the mounting rod and located between the magnetic levitation support coil and the levitation superconducting coil. The second tray is slidably connected to the mounting rod and located below the levitation superconducting coil. The output end of the lifting mechanism is connected to the bottom of the second tray and is used to drive the second tray to move along the mounting rod to lift the levitation superconducting coil. The first tray is used to limit the upward position of the levitation superconducting coil.

[0008] Preferably, as a further improvement of the present invention, a balance control coil assembly is provided on the circumferential inner wall of the vacuum chamber. The balance control coil assembly includes a first balance control coil, a second balance control coil, a third balance control coil, a fourth balance control coil, and a fifth balance control coil arranged sequentially from top to bottom. The first balance control coil, the second balance control coil, the third balance control coil, the fourth balance control coil, the fifth balance control coil, the inductive charging coil, the levitation superconducting coil, and the magnetic levitation support coil are all coaxially arranged.

[0009] Preferably, as a further improvement of the present invention, a first Helmholtz coil is connected to the bottom of the sealed chamber, and a second Helmholtz coil is connected to the top of the sealed chamber, wherein the first Helmholtz coil, the second Helmholtz coil, and the levitation superconducting coil are coaxially arranged.

[0010] Preferably, as a further improvement of the present invention, the outer wall of the sealed chamber is provided with a first dipole field attitude control coil and multiple sets of second dipole field attitude control coils. The first dipole field attitude control coil is connected to the circumferential outer wall of the sealed chamber, and the multiple sets of second dipole field attitude control coils are evenly distributed around the sealed chamber. Each set of second dipole field attitude control coils is arranged along the longitudinal outer wall of the sealed chamber and is arranged at 90° with the first dipole field attitude control coil.

[0011] Preferably, as a further improvement of the present invention, a first flange connection port is provided on the side wall of the sealed chamber, the first flange connection port being used to connect to an external neutral beam injection heating system.

[0012] Preferably, as a further improvement of the present invention, a second flange connection port is provided on the side wall of the sealed chamber, the second flange connection port being used to connect to an external electronic or ion cyclone heating system.

[0013] Preferably, as a further improvement of the present invention, the top of the sealed chamber is provided with a third flange connection port, which is used to connect to an external vacuum pumping device.

[0014] Compared with the prior art, the beneficial effects of the present invention are: 1. This invention employs a method for confining, stabilizing, and controlling high-temperature plasma using a dipole magnetic field to achieve a new approach to controlled nuclear fusion and designs a suspended dipole field plasma device. By using a single suspended superconducting coil magnet to generate a poloidal magnetic field to constrain the configuration, the physical characteristics and operational control laws of the fusion plasma are experimentally tested and studied. The entire device involves only three ring superconducting coils: an induction charging coil, a suspended superconducting coil, and a magnetically levitated support coil, significantly reducing system complexity and manufacturing costs. Therefore, a higher net energy gain Q value is achieved through a simplified and compact structural design. The dipole field plasma confinement principle is based on Hamiltonian dynamics of celestial plasma and the principle of minimum energy, with the confinement coming from the poloidal magnetic field to achieve the excellent stability performance of the dipole field plasma.

[0015] 2. By generating a natural magnetic interface through a levitated superconducting coil magnet, the complex toroidal field coil system of the traditional tokamak is replaced. The plasma confinement mainly comes from the internal pinch caused by the attenuation of the magnetic field on the outside of the levitated superconducting coil magnet, while the tokamak confinement relies on the plasma loop current. The two confinement principles are different. Since there is no driving current, the dipole plasma spontaneously forms a high specific pressure stable configuration, which fundamentally suppresses magnetohydrodynamic instabilities such as tearing mode and peeling mode, and improves operational safety.

[0016] 3. The device can realize tritium-free D-He3 (deuterium-helium-3) reaction and DD (deuterium-deuterium) reaction. The tritium-free self-sufficiency β can exceed 100%. Compared with the tokamak, which only supports DT (deuterium-tritium) reaction, it will not produce 14MeV of neutrons, thereby reducing the radiation damage to the first wall material.

[0017] 4. Since the dipole plasma is confined in the magnetic field region outside the levitation superconducting coil, τp (particle confinement time) / τe (energy confinement time) ≪ 1, which means that the time for particles to be confined is much shorter than the time for energy to be confined. The "ash" produced by the reaction is quickly discharged before it takes away a large amount of energy, thus having the advantage of high ash removal efficiency.

[0018] 5. Three-dimensional stable positioning is achieved through active electromagnetic levitation technology, eliminating plasma contamination and heat loss caused by the support structure in traditional devices, and significantly extending the constraint time (up to 300 seconds in experiments).

[0019] 6. Without the high heat load limitation of the first wall, the radius of the vacuum chamber is much larger than the radius of the plasma confinement region, which greatly reduces the peak heat load of the first wall. Attached Figure Description

[0020] Figure 1 This is a three-dimensional structural schematic diagram of a suspended dipole field plasma device according to the present invention.

[0021] Figure 2 This is a three-dimensional structural schematic diagram of a suspended dipole field plasma device according to the present invention from another perspective. Detailed Implementation

[0022] The following is combined with Figures 1-2 The specific embodiments of the present invention will be described in detail below. In the description of the invention, it should be understood that the terms "center", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", etc., indicating the orientation or positional relationship are based on the orientation or positional relationship shown in the accompanying drawings, and are only for the convenience of describing the present invention and simplifying the description, and are not intended to indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation, and therefore should not be construed as a limitation of the present invention.

[0023] The terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature; in the description of the invention, unless otherwise stated, "a plurality of" means two or more.

[0024] Example 1 like Figure 1 As shown, this embodiment of the invention provides a suspended dipole field plasma device, including a sealed chamber 4, an induction charging coil 21, a suspended superconducting coil 23, a height adjustment component, and a magnetic levitation support coil 10. The sealed chamber 4 has a vacuum chamber 15 formed inside by evacuation. A cylindrical mounting chamber 1 extends downward from the bottom of the sealed chamber 4, and the sealed chamber 4 has an inflation port 13 for connecting to an external gas supply device. The induction charging coil 21 is disposed inside the cylindrical mounting chamber 1. The suspended superconducting coil 23 is disposed inside the induction charging coil 21. The height adjustment component is disposed inside the vacuum chamber 15, and the height adjustment component has… It has a lifting end, which is detachably connected to the levitation superconducting coil 23. It is used to charge the levitation superconducting coil 23 through the induction charging coil 21 and adjust the height of the levitation superconducting coil 23. The magnetic levitation support coil 10 is set on the top of the sealed chamber 4 and is used to magnetically position the levitation superconducting coil 23 after it has been adjusted by the height adjustment component, so that the levitation superconducting coil 23 is suspended in the vacuum chamber 15. The dipole confinement magnetic field generated by the levitation superconducting coil 23 will confine the plasma 22 generated by the discharge gas filled through the gas filling port 13, so that the plasma 22 is located outside the levitation superconducting coil 23.

[0025] In this embodiment, the spatial positioning and energy supply of the levitation superconducting coil are achieved by combining non-contact magnetic levitation with inductive power supply, and the axisymmetric dipole magnetic field generated by the coil is used to efficiently confine the high-temperature plasma. This device abandons the complex toroidal and longitudinal field coil systems found in traditional tokamas, employing a single superconducting toroidal magnet as the main confinement source. The entire device involves only three toroidal superconducting coils: an induction charging coil 21, a levitation superconducting coil 23, and a magnetic levitation support coil 10, significantly reducing system complexity and manufacturing costs. The entire device operates in a high vacuum environment. After being inductively charged by the induction charging coil 21, the levitation superconducting coil 23 is lifted by a height adjustment component and then held in place by the electromagnetic force generated by the magnetic levitation support coil 10, thus suspending itself in the central region of the vacuum chamber. Deuterium, helium-3, or hydrogen gases are injected into the vacuum chamber 15 through the gas filling port 13 via an external gas supply system. Under radio frequency excitation or other starting methods, the gas is ionized and forms a plasma state. The strong magnetic field generated by the levitation superconducting coil 23 itself forms a closed magnetic field line structure, constituting a natural magnetic interface, thereby confining the plasma 22 to the space outside the magnet of the levitation superconducting coil 23, preventing the plasma 22 from directly contacting the inner wall of the device, and reducing the problems of impurity intrusion and concentrated heat load.

[0026] The sealed chamber 4 is a pressure vessel with an integral structure, made of stainless steel, possessing excellent airtightness and mechanical strength. A non-magnetic material with high resistivity and low magnetic permeability is selected as the structural material for the vacuum chamber. Under the action of an external vacuum pump, a high-pressure vacuum environment, namely vacuum chamber 15, is formed inside. This vacuum chamber 15 is used to isolate external interference and ensure the clean electromagnetic environment required for plasma operation. The cylindrical mounting chamber 1, extending downwards from the bottom of the sealed chamber 4, mainly houses the induction charging coil 21. Physical isolation prevents electromagnetic interference or heat conduction between the coil and the plasma inside the vacuum chamber, ensuring the induction charging coil 21 is securely installed and has good heat dissipation. The gas filling port 13 is located on the side wall or bottom of the sealed chamber 4 and can be connected to an external gas storage tank and mass flow controller via a metal bellows.

[0027] The induction charging coil 21 is fixed to the inner peripheral wall of the cylindrical mounting chamber 1. The function of the induction charging coil 21 is to couple energy to the suspended superconducting coil 23 located inside it through electromagnetic induction before the experiment starts, so as to achieve wireless charging until the current reaches the specified value. The induction charging coil 21 uses high-temperature superconductivity to reduce power loss.

[0028] The height adjustment component is located inside the vacuum chamber 15. Its lifting end is detachably connected to the levitation superconducting coil 23 and is used to adjust the vertical position of the levitation superconducting coil 23. After the levitation superconducting coil 23 is charged, it is lifted upward to the position where it is attracted and positioned by the magnetic levitation support coil 10. Specifically, the height adjustment assembly includes a mounting rod 12, a first tray 14, a second tray 2, and a lifting mechanism. The mounting rod 12 is vertically inserted through the center of the inductive charging coil 21, the levitation superconducting coil 23, and the magnetic levitation support coil 10. The lower end of the mounting rod 12 is fixed to the inner bottom surface of the cylindrical mounting chamber 1. The first tray 14 is fixed on the mounting rod 12 and is located between the magnetic levitation support coil 10 and the levitation superconducting coil 23. The second tray 2 is slidably connected to the mounting rod 12 and is located below the levitation superconducting coil 23. The output end of the lifting mechanism is connected to the bottom of the second tray 2 and is used to drive the second tray 2 to move along the mounting rod 12 to lift the levitation superconducting coil 23. The first tray 14 is used to limit the rising position of the levitation superconducting coil 23. The lifting mechanism can be a screw lifting assembly, an electric push rod, or other structures.

[0029] When adjusting the height using the height adjustment component, the second tray 2 is used to lift the levitation superconducting coil 23, and the position of the levitation superconducting coil 23 is adjusted in the initial stage so that it is inductively charged by the induction charging coil 21. After the charging is completed and the levitation superconducting coil 23 enters the superconducting state, the lifting mechanism drives the second tray 2 to lift the levitation superconducting coil 23 upward. Since the first tray 14 is fixed on the mounting rod 12, the first tray 14 is used to limit the levitation superconducting coil 23 so that it is attracted by the magnetic levitation support coil 10 after reaching the position. After the gravity and electromagnetic force of the levitation superconducting coil 23 are balanced and stabilized, the lifting mechanism drives the second tray 2 to move downward and exit the bearing state, so that the levitation superconducting coil 23 is in a levitation state.

[0030] The magnetic levitation support coil 10 is installed at the top of the sealed chamber 4. When energized, it generates a downward repulsive magnetic field or an upward attractive force below it to counteract the gravity of the levitation superconducting coil 23 and achieve stable levitation. A dynamic feedback control system exists between this coil and the levitation superconducting coil 23. A Hall sensor monitors the distance between them in real time and adjusts the excitation current of the magnetic levitation support coil 10 to maintain a constant levitation gap. The magnetic levitation method eliminates the vibration, frictional particle contamination, and thermal bridging effects caused by traditional mechanical supports, greatly improving plasma purity and confinement time. In the levitation state, the levitation superconducting coil 23 is completely detached from physical contact and can be finely adjusted in three-dimensional space to adapt to different experimental conditions.

[0031] Through the above technical solution, this application achieves the following: a levitation superconducting coil 23 is stably suspended in the central region of the vacuum chamber 15 without mechanical support, and a working current is provided to it through inductive charging, generating a high-intensity, axisymmetric dipole confinement magnetic field. Because this magnetic field has a naturally closed magnetic field line structure, it can spontaneously form a magnetic interface, confining the plasma to the outer region of the levitation superconducting coil 23, such that τp (particle confinement time) / τe (energy confinement time) ≪ 1. This means that the time the particles are confined is much shorter than the time the energy is confined, and the "ash" produced by the reaction is rapidly expelled before carrying away a large amount of energy, resulting in high ash removal efficiency. In contrast, the tokamak uses a complex toroidal field coil system, where the plasma is completely enclosed inside the toroidal magnet, resulting in τp (particle confinement time) / τe (energy confinement time) being approximately 2~5. The time the particles are confined is longer than the time the energy is confined, making ash removal difficult.

[0032] Meanwhile, this configuration generates a natural magnetic interface through the levitated superconducting coil 23 magnet, replacing the complex toroidal field coil system of traditional tokamak. It does not rely on the internal current of the plasma to maintain the magnetic field configuration. This design enables the plasma 22 to spontaneously form a high specific pressure stable configuration, fundamentally suppressing magnetohydrodynamic instabilities such as tearing mode and peeling mode, and improving operational safety. The overall structure of the device is compact, requiring only a few key coils to achieve high-performance magnetic confinement. Compared with traditional tokamak, it greatly simplifies the system architecture, reduces construction and maintenance costs, and achieves a higher net energy gain Q value with a simplified and compact structural design.

[0033] Furthermore, the suspended dipole field can realize tritium-free D-He3 (deuterium-helium-3) reaction and DD (deuterium-deuterium) reaction. Compared with the tokamak, which only supports DT (deuterium-tritium) reaction, it does not produce 14MeV of neutrons, thereby reducing irradiation damage to the first wall material.

[0034] In another embodiment of the present invention, a balance control coil assembly is provided on the circumferential inner wall of the vacuum chamber 15. The balance control coil assembly includes a first balance control coil 9, a second balance control coil 16, a third balance control coil 18, a fourth balance control coil 19 and a fifth balance control coil 20 arranged sequentially from top to bottom. The first balance control coil 9, the second balance control coil 16, the third balance control coil 18, the fourth balance control coil 19 and the fifth balance control coil 20, the inductive charging coil 21, the levitation superconducting coil 23 and the magnetic levitation support coil 10 are all coaxially arranged.

[0035] This embodiment employs a multi-level distribution of balance control coil assemblies along the circumferential inner wall of the vacuum chamber 15. All balance control coils are strictly coaxially aligned with the induction charging coil 21, the central floating coil 23, and the magnetic levitation support coil 10. This coaxial configuration ensures a high degree of axial symmetry in the entire system's magnetic field, avoiding additional lateral torque or eddy current effects caused by eccentric arrangement. This coaxial layout design reduces interference with the stable levitation state of the central floating coil 23, enabling precise control of the magnetic field environment surrounding the central floating coil 23. This structure aims to address the problem of instability phenomena such as tilting and shifting caused by external disturbances or internal magnetic field asymmetry in the levitation state of the central floating coil, thereby ensuring the integrity and stability of the dipole field configuration.

[0036] In another embodiment of the present invention, a first Helmholtz coil 3 is connected to the bottom of the sealed chamber 4, and a second Helmholtz coil 8 is connected to the top of the sealed chamber 4. The first Helmholtz coil 3, the second Helmholtz coil 8 and the levitation superconducting coil 23 are coaxially arranged. By using the first Helmholtz coil 3 and the second Helmholtz coil 8, the shape of the outer magnetic surface of the plasma 22 can be changed during the operation of the device in order to meet the experimental requirements of different magnetic surface shapes.

[0037] In another embodiment of the present invention, a first dipole field attitude control coil 6 and multiple sets of second dipole field attitude control coils 7 are provided on the outer wall of the sealed chamber 4. The first dipole field attitude control coil 6 is connected to the circumferential outer wall of the sealed chamber 4, and the multiple sets of second dipole field attitude control coils 7 are evenly distributed around the sealed chamber 4. Each set of second dipole field attitude control coils 7 is arranged along the longitudinal outer wall of the sealed chamber 4 and is set at a 90° angle to the first dipole field attitude control coil 6. To achieve spatial attitude stability control of the levitation superconducting coil 23 in the levitation state, since the levitation superconducting coil 23 is in a non-contact magnetic levitation state during operation, it is susceptible to slight rotation or tilting due to external electromagnetic noise, residual gas flow and start-up transient torque. If not corrected in time, it will lead to the inaccuracy of the dipole confinement magnetic field. Therefore, the first dipole field attitude control coil 6 and multiple sets of second dipole field attitude control coils 7 can suppress the reversal, oscillation and tilting of the dipole field coil during the operation of the device, so that it remains relatively stationary in the center position of the vacuum chamber.

[0038] In another embodiment of the present invention, in order to provide the density of plasma 22, a first flange connection port 5 is provided on the side wall of the sealed chamber 4. The first flange connection port 5 is used to connect to the external neutral beam injection heating system. After connecting to the external neutral beam injection heating system through the first flange connection port 5, the neutral beam experimental gas is first accelerated through the Laval nozzle. During the acceleration process, the neutral beam experimental gas is heated. The heated neutral beam experimental gas is sent into the vacuum chamber 15 to realize the particle feeding and energy injection process.

[0039] In another embodiment of the present invention, similarly, in order to generate plasma and inject it into the vacuum chamber and increase the density of the plasma inside the vacuum chamber 15, a second flange connection port 17 is provided on the side wall of the sealed chamber 4. The second flange connection port 17 is used to connect to an external electronic or ion cyclotron heating system. After connecting to the external electronic or ion cyclotron heating system through the second flange connection port 17, the waves released by the external electronic or ion cyclotron heating system interact with the plasma, causing the plasma to absorb energy and further heat the plasma, thereby realizing the particle feeding and energy injection process.

[0040] In another embodiment of the present invention, a third flange connection port 11 is provided on the top of the sealed chamber 4. The third flange connection port 11 is used to connect to an external vacuum pumping device. Since the vacuum chamber 15 needs to be kept in a vacuum state during the operation of the device, the vacuum degree of the vacuum chamber 15 is stabilized by connecting the flange port 11 to the external vacuum pumping system.

[0041] The experimental procedure for this device is as follows: The device is evacuated to a vacuum state, maintaining a high vacuum inside the vacuum chamber 15. The first Helmholtz forming coil 3, the second Helmholtz coil 8, the magnetic levitation support coil 10, the inductive charging coil 21, the first balance control coil 9, the second balance control coil 16, the third balance control coil 18, the fourth balance control coil 19, and the fifth balance control coil 20 are energized to excite the magnetic field. The inductive charging coil 21 charges the levitation superconducting coil 23. After charging, the lifting mechanism moves the second tray 2 to lift the levitation superconducting coil 23 upwards. The first tray 14 limits the position of the levitation superconducting coil 23. Once the gravity and electromagnetic force of the levitation superconducting coil 23 are balanced and stable, the lifting mechanism moves the second tray 22 downwards away from the levitation superconducting coil 23, leaving the levitation superconducting coil 23 in a suspended state. Discharge gas is introduced into the device through a gas supply device. Radio frequency waves excite and couple the gas to generate plasma, which is then ionized. A dipole confinement magnetic field generated by the magnet of the levitation superconducting coil 23 confines the plasma 22 to the outside of the levitation superconducting coil 23 and inside the vacuum chamber 15. The density and temperature of the confined plasma 22 are increased by a neutral beam injection heating system and an electron or ion cyclotron heating system. After completing the physical experimental testing and diagnosis of the device, the lifting mechanism is controlled to raise the second tray 2 to receive the levitation superconducting coil 23. Then, the magnetic attraction of the magnetic levitation support coil 10 to the levitation superconducting coil 23 is released, and the lifting mechanism lowers the second tray 2, moving the levitation superconducting coil 23 into the cylindrical mounting chamber 1.

[0042] The above-disclosed embodiments are merely preferred embodiments of the present invention. However, the embodiments of the present invention are not limited thereto, and any variations that can be conceived by those skilled in the art should fall within the protection scope of the present invention.

Claims

1. A suspended dipole field plasma device, characterized in that, include: The sealed chamber has a vacuum chamber inside, and the bottom of the sealed chamber extends downward to form a cylindrical installation chamber. The sealed chamber has an inflation port for connecting to an external air supply device. An inductive charging coil is disposed inside the cylindrical mounting cavity; A levitated superconducting coil is disposed inside the inductive charging coil; A height adjustment component is disposed in the vacuum chamber. The height adjustment component has a lifting end, which is connected to the levitation superconducting coil. It is used to adjust the height position of the levitation superconducting coil after charging it through the induction charging coil. A magnetic levitation support coil is installed at the top of the sealed chamber to magnetically position the levitation superconducting coil, which has been adjusted by the height adjustment component, so that the levitation superconducting coil is suspended in the vacuum chamber. The dipole confinement magnetic field generated by the levitation superconducting coil will confine the plasma generated by the discharge gas introduced through the gas filling port, so that the plasma is located outside the levitation superconducting coil.

2. The suspended dipole field plasma device according to claim 1, characterized in that, The height adjustment assembly includes a mounting rod, a first tray, a second tray, and a lifting mechanism. The mounting rod is vertically inserted through the center of the inductive charging coil, the levitation superconducting coil, and the magnetic levitation support coil. The lower end of the mounting rod is fixed to the inner bottom surface of the cylindrical mounting chamber. The first tray is fixed on the mounting rod and located between the magnetic levitation support coil and the levitation superconducting coil. The second tray is slidably connected to the mounting rod and located below the levitation superconducting coil. The output end of the lifting mechanism is connected to the bottom of the second tray and is used to drive the second tray to move along the mounting rod to lift the levitation superconducting coil. The first tray is used to limit the upward position of the levitation superconducting coil.

3. The suspended dipole field plasma device according to claim 1, characterized in that, The vacuum chamber is provided with a balance control coil assembly on its circumferential inner wall. The balance control coil assembly includes a first balance control coil, a second balance control coil, a third balance control coil, a fourth balance control coil, and a fifth balance control coil arranged sequentially from top to bottom. The first balance control coil, the second balance control coil, the third balance control coil, the fourth balance control coil, the fifth balance control coil, the inductive charging coil, the levitation superconducting coil, and the magnetic levitation support coil are all coaxially arranged.

4. The suspended dipole field plasma device according to claim 3, characterized in that, The bottom of the sealed chamber is connected to a first Helmholtz coil, and the top of the sealed chamber is connected to a second Helmholtz coil. The first Helmholtz coil, the second Helmholtz coil, and the levitation superconducting coil are coaxially arranged.

5. The suspended dipole field plasma device according to claim 4, characterized in that, The outer wall of the sealed chamber is provided with a first dipole field attitude control coil and multiple sets of second dipole field attitude control coils. The first dipole field attitude control coil is connected to the circumferential outer wall of the sealed chamber. The multiple sets of second dipole field attitude control coils are evenly distributed around the sealed chamber, and each set of second dipole field attitude control coils is arranged along the longitudinal outer wall of the sealed chamber and is set at 90° with the first dipole field attitude control coil.

6. The suspended dipole field plasma device according to claim 1, characterized in that, The sealed chamber has a first flange connection port on its side wall, which is used to connect to an external neutral beam injection heating system.

7. The suspended dipole field plasma device according to claim 1, characterized in that, A second flange connection port is provided on the side wall of the sealed chamber, which is used to connect to an external electronic or ion cyclone heating system.

8. The suspended dipole field plasma device according to claim 1, characterized in that, The top of the sealed chamber is provided with a third flange connection port, which is used to connect to an external vacuum pumping device.

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