divertor coil module and device

Abstract

The application discloses a divertor coil module and a device, and relates to the field of plasma. In the prior art, the research on the divertor physics and engineering of the current linear device is mainly concentrated on the plasma and material interaction, the linear device does not have closed magnetic force lines, the plasma current is weak, and the linear device does not have the divertor topological structure and magnetic field configuration of the toroidal device. The technical scheme provided by the application is as follows: the divertor coil module comprises a poloidal field coil, an auxiliary coil, a divertor coil and a vacuum chamber; the vacuum chamber is in a cylindrical structure; the poloidal field coil is used for providing a uniform magnetic field along the axial direction of the cylindrical structure when being turned on; the divertor coil is used for providing a magnetic field in the direction opposite to the direction of the uniform magnetic field when being turned on, and the magnetic field is superposed with the uniform magnetic field to generate a magnetic zero point; and the auxiliary coil is used for providing a magnetic field for adjusting the magnetic field configuration structure of the divertor when being turned on. The application is suitable for being applied to an experimental platform for studying the divertor physics on the linear device.

Description

Technical Field

[0001] It involves the field of plasma, specifically electromagnetic systems. Background Technology

[0002] Currently, energy is a critical issue restricting the development of human society, and the exploration of fusion energy is an important path for achieving energy freedom. The divertor configuration is an advanced tokamak discharge configuration that avoids direct contact between the plasma and the device wall confines by forming a magnetic null point (X-point), reducing material adhesion and impurity backflow. In the divertor configuration, the high-temperature plasma crossing the last closed magnetic surface, especially the helium ash produced by the reaction, strikes the divertor target along the magnetic field lines and is then expelled from the device by the vacuum system.

[0003] A series of key scientific questions surrounding divertor configurations influence and constrain the operation of high-parameter fusion devices, particularly future commercial fusion reactors. These questions include, but are not limited to: target heat load, impurity backflow, the impact of plasma-divertor interaction on core transport and confinement, and ash and impurity removal technologies. Solving these physical and engineering problems requires extensive and meticulous experimental research as a foundation.

[0004] Tokamak and other toroidal devices suffer from poor controllability and adjustability of experimental parameters. Diagnostic methods are limited by experimental conditions and windows, making it difficult to conduct precise and repeatable experiments. In particular, the coupled influence of numerous experimental conditions makes it impossible to test specific physical phenomena and engineering technologies. Furthermore, existing toroidal devices struggle to achieve the experimental conditions of long-pulse steady-state discharge, high heat load, and particle adhesion at the fusion reactor level, which also limits research progress on divertor physics problems.

[0005] In comparison, linear plasma facilities have unique advantages in fine physics and engineering research, and have made significant progress in studying plasma-material interactions. As small-scale devices for such research, linear plasma facilities offer advantages such as high parameter controllability, reproducible results, and short experimental cycles. Currently, many domestic institutions, including the Southwestern Institute of Physics of the Nuclear Industry, the Institute of Plasma Physics of the Chinese Academy of Sciences, the University of Science and Technology of China, Beijing University of Aeronautics and Astronautics, Sichuan University, and Harbin Institute of Technology, have built linear plasma facilities for different research directions. Internationally, representative similar facilities include CSDX at UCSD, LAPD at UCLA, and PANTA at Kyushu University.

[0006] Current research on divertor physics and engineering using linear devices mainly focuses on the interaction between plasma and materials. This is primarily because linear devices lack closed magnetic field lines, have weaker plasma currents, and do not possess the divertor topology and magnetic field configuration of ring devices. Summary of the Invention

[0007] To address the shortcomings of existing technologies, current research on the physics and engineering of linear divertors primarily focuses on plasma-material interactions. This is mainly because linear divertors lack closed magnetic field lines, resulting in weaker plasma currents and the absence of the divertor topology and magnetic field configuration found in ring-shaped devices. The technical solution provided by this invention is as follows:

[0008] A divertor coil module, the module comprising: a poloidal field coil, an auxiliary coil, a divertor coil, and a vacuum chamber;

[0009] The vacuum chamber has a cylindrical structure, and the poloidal field coil, auxiliary coil, and divertor coil are located inside the cylindrical structure.

[0010] The poloidal field coil is used to provide a uniform magnetic field along the axis of the cylindrical structure when it is turned on;

[0011] The divertor coil is used to provide a magnetic field in the opposite direction to the uniform magnetic field when it is turned on, and it is superimposed with the uniform magnetic field to generate a magnetic zero point.

[0012] The auxiliary coil is used to provide a magnetic field for adjusting the magnetic field configuration of the divertor when it is turned on.

[0013] Furthermore, a preferred embodiment is provided in which the vacuum chamber has a cylindrical structure.

[0014] Furthermore, a preferred embodiment is provided, wherein the poloidal field coil includes six sets of wires, all of which are parallel to the axis of the cylindrical structure; a plane perpendicular to the axis is defined as a projection plane, and the virtual image projected onto the projection plane by the six sets of wires is the six vertices of a regular hexagon.

[0015] Furthermore, a preferred embodiment is provided in which all six sets of conductors are single-turn coils.

[0016] Furthermore, a preferred embodiment is provided in which the divertor coil includes two sets of wires, both sets of wires being parallel to the axis of the cylindrical structure.

[0017] Furthermore, a preferred embodiment is provided in which both sets of conductors are single-turn coils.

[0018] Furthermore, a preferred embodiment is provided in which the auxiliary coil includes two sets of wires, both sets of wires being parallel to the axis of the cylindrical structure.

[0019] Furthermore, a preferred embodiment is provided in which both sets of conductors are single-turn coils.

[0020] Based on the same inventive concept, the present invention also provides a divertor coil device, the device comprising: a main magnetic field coil and a divertor coil module, wherein the divertor coil module is the divertor coil module described above, and the main magnetic field coil is sleeved outside the vacuum chamber.

[0021] Furthermore, a preferred embodiment is provided in which there are five main magnetic field coils arranged in parallel to each other, and the length of the vacuum chamber, the poloidal field coil, the auxiliary coil and the divertor coil along the axial direction is greater than the distance between the beginning and end of the main magnetic field coil along the axial direction.

[0022] The advantages of this invention are:

[0023] The divertor coil device provided by this invention achieves, for the first time in a linear device, a complete divertor magnetic field configuration including LCFS and the X point, solving the problems of non-closed magnetic field lines and a single magnetic field structure in previous linear devices. This provides a new method for experimental research on tokamak divertors. The spiral magnetic field structure generated by the interaction of the main magnetic field and the poloidal field realized in this device is similar to the magnetic field structure of the main region in a tokamak, capable of exciting plasma modes such as drift waves, exchange instabilities, and balloon modes. The study of turbulent transport is key to improving the confinement capability of tokamaks and ultimately realizing controlled nuclear fusion technology. On the other hand, the complete tunable divertor structure realized in the device provides experimental conditions for studying the influence of topological properties on plasma modes, transport, and confinement performance, and provides experimental evidence for fusion engineering problems such as impurity transport suppression in divertor targets and ash removal from combustion plasma. This is beneficial for our research on tokamak divertor problems, solving issues such as tokamak confinement, thermal energy deposition, and impurity removal.

[0024] It is suitable for use in experimental platforms for studying divertor physics on linear devices. Attached Figure Description

[0025] Figure 1 A cross-sectional schematic diagram of the divertor coil module provided in Embodiment 1;

[0026] Figure 2 A cross-sectional schematic diagram of the divertor coil device provided in Embodiment Nine;

[0027] Figure 3 A front view of the divertor coil assembly provided in Embodiment Nine;

[0028] Figure 4 A schematic diagram of the magnetic field results of the divertor coil device provided in Embodiment Nine;

[0029] Figure 5 A schematic diagram of the magnetic field results of the divertor coil device provided in Embodiment Nine under auxiliary coil adjustment;

[0030] Figure a shows the state with the left auxiliary coil turned on, and Figure b shows the state with the right auxiliary coil turned on.

[0031] Figure 6 A cross-sectional schematic diagram of an alternative to the divertor coil device mentioned in Embodiment Nine;

[0032] Figure 7 for Figure 6 A schematic diagram of the magnetic field results;

[0033] Figure 8 for Figure 7 A schematic diagram of the magnetic field results under auxiliary coil adjustment;

[0034] Figure c shows the state where the left auxiliary coil is turned on, and Figure d shows the state where the right auxiliary coil is turned on.

[0035] In this diagram, 1 represents the vacuum chamber, 2 represents the poloidal field coil, 3 represents the auxiliary coil, 4 represents the divertor coil, and 5 represents the main magnetic field coil. Detailed Implementation

[0036] To make the advantages and benefits of the technical solution provided by the present invention clearer, the technical solution provided by the present invention will now be described in further detail with reference to the accompanying drawings. Specifically:

[0037] Implementation Method 1: Combination Figure 1 This embodiment describes a divertor coil module, which includes: a poloidal field coil 2, an auxiliary coil 3, a divertor coil, and a vacuum chamber 1.

[0038] The vacuum chamber 1 has a cylindrical structure, and the poloidal field coil 2, auxiliary coil 3 and divertor coil are located inside the cylindrical structure.

[0039] The poloidal field coil 2 is used to provide a uniform magnetic field along the axis of the cylindrical structure when it is turned on;

[0040] The divertor coil is used to provide a magnetic field in the opposite direction to the uniform magnetic field when it is turned on, and it is superimposed with the uniform magnetic field to generate a magnetic zero point.

[0041] The auxiliary coil 3 is used to provide a magnetic field for adjusting the magnetic field configuration of the divertor when it is turned on.

[0042] In this method, the poloidal magnetic field coil can be replaced by a straight conductor located at the center. This method can create a current path connected to the atmosphere by passing a stainless steel tube through the center, reducing the technical difficulty of the conductor passing through the vacuum wall. Furthermore, since the coil is located in the atmospheric environment, ceramic coating is unnecessary, increasing the current density and further enhancing the poloidal magnetic field strength. However, because the central region is occupied by the coil, non-contact, high-parameter, low-collision plasma sources such as helical waves cannot be used. Alternatives such as hot cathode sources and capacitively coupled discharges are required. This method is not suitable for studying turbulence in the edge region, but it can still be used for research on target-plasma interaction and scraped layer transport.

[0043] The coil is manufactured using an oxygen-free copper tube coated with alumina ceramic and pre-cleaned with plasma to remove volatile impurities, especially organic impurities. Water cooling utilizes Green connectors, and the coil leads are mechanically crimped with galvanized connectors to ensure optimal contact. The vacuum current leads are axially sealed with trapezoidal fluororubber, obtained through non-standard processing. The power supply is custom-made, with a power rating of 50kW and a rated current of 600A.

[0044] Implementation Method Two: Combination Figure 1 This embodiment is a further definition of the divertor coil module provided in Embodiment 1, wherein the vacuum chamber 1 has a cylindrical structure.

[0045] Implementation Method 3: Combination Figure 1 This embodiment further defines the divertor coil module provided in Embodiment 1. The poloidal field coil 2 includes six sets of wires, all of which are parallel to the axis of the cylindrical structure. The plane perpendicular to the axis is defined as the projection plane, and the virtual image projected onto the projection plane by the six sets of wires is the six vertices of a regular hexagon.

[0046] Implementation Method 4: This implementation method further defines the divertor coil module provided in Implementation Method 3, wherein all six sets of wires are single-turn coils.

[0047] Implementation Method 5: Combination Figure 1 This embodiment further defines the divertor coil module provided in Embodiment 1. The divertor coil includes two sets of wires, both of which are parallel to the axis of the cylindrical structure.

[0048] Implementation Method Six: This implementation method is a further limitation of the divertor coil module provided in Implementation Method Five, wherein both sets of wires are single-turn coils.

[0049] Implementation Method Seven: Combination Figure 1This embodiment further defines the divertor coil module provided in Embodiment 1. The auxiliary coil 3 includes two sets of wires, both of which are parallel to the axis of the cylindrical structure.

[0050] Implementation Method 8: This implementation method is a further limitation of the divertor coil module provided in Implementation Method 7, wherein both sets of wires are single-turn coils.

[0051] Implementation Method Nine: Combination Figure 2-8 This embodiment describes a divertor coil device, which includes a main magnetic field coil 5 and a divertor coil module. The divertor coil module is the same as the divertor coil module provided in Embodiment 1. The main magnetic field coil 5 is sleeved outside the vacuum chamber 1.

[0052] The hardware system of this invention consists of three parts:

[0053] The first part is the poloidal field coil 2. In the linear device, which is essentially a divertor coil device, the main magnetic field coils 5 are arranged in a longitudinal straight line. When activated, these coils provide a uniform magnetic field along the longitudinal direction. To add a poloidal magnetic field to this uniform magnetic field, the device generates a magnetic field configuration similar to the spiral structure in a tokamak device. This requires the addition of a longitudinally positioned poloidal field coil 2 to provide the poloidal magnetic field component. The main part of the designed poloidal field coil 2 is located within the vacuum chamber, longitudinally traversing five sets of main magnetic field coils 5. The poloidal field coil 2 consists of six sets of wires, each located at one of the six vertices of a regular hexagon with a side length of 100 mm. The coils are parallel to each other. The center of the coil group, i.e., the center of the regular hexagon, is located 140 mm above the center of the main magnetic field coil 5 and 40 mm to the right. The six sets of coils have a symmetrical structure, with three sets on each side of the center. Each coil set uses a single-turn coil with a maximum current Imax(A) = 600 Ω and a coil diameter of 20 mm.

[0054] The second part is the divertor magnetic field coil. In a tokamak, the divertor magnetic field is generated by the addition of a circumferential current, producing a reverse magnetic field that superimposes with the poloidal field to create a magnetic null point, or X point, which represents the divertor configuration. In a linear configuration, divertor coil 4 is designed to pass longitudinally through the vacuum chamber, with the coil close to the bottom of the chamber. The coil portion inside the chamber is parallel to the poloidal field coil 2, and the current flows in the same direction as the poloidal field coil 2. This ensures that the magnetic fields generated by the poloidal field coil 2 and the divertor coil 4 in the middle section are opposite, and their superposition produces the divertor magnetic field configuration. The divertor magnetic field coil is designed with two sets of parallel wires, symmetrically distributed 30mm on each side of the perpendicular line in the device. Each set of divertor coil 4 uses a single-turn coil, with a designed maximum current Imax(A) = 600 Ω and a coil diameter of 24mm.

[0055] The third part is the X-point adjustment coil, also known as auxiliary coil 3. After the divertor magnetic field configuration is formed, the shape and vertical position of the central X-point are mainly determined by the shape and current of the poloidal field coil 2 and the divertor coil 4. Since the currents in these two coils are relatively large, adjusting the divertor magnetic field structure using them is relatively difficult. Therefore, auxiliary coil 3 is added to both sides of the X-point of the divertor under rated parameters to adjust the divertor magnetic field configuration. Auxiliary coil 3 passes longitudinally through the straight-line device, parallel to the poloidal field coil 2, with the current in the opposite direction. Auxiliary coil 3 consists of two sets of wires, with a spacing of 100mm between them. The center of the wires is 160mm vertically from the center of the main coil and 10mm laterally from the perpendicular bisector. The vertical difference between the two wires is 15mm. Each set of auxiliary coil 3 is designed with a single-turn coil, a maximum designed current Imax(A) = 300, and a single coil diameter of 15mm.

[0056] The vacuum high-current lead wire serves as the main magnetic field coil 5. An internal water-cooled copper coil generates a stable magnetic field, and surface insulation is achieved using alumina ceramic spraying technology. Impurities adsorbed on the alumina ceramic are cleaned through plasma pre-discharge. Furthermore, all external conductors are completely shielded to reduce the impact of stray fields on the internal magnetic field. Axial insulation sealing is employed when the coil passes through the vacuum wall, with boron nitride ceramic insulating sleeves buffering instantaneous stress. Trapezoidal fluororubber is used to ensure the vacuum level and electromagnetic insulation of the chamber.

[0057] The purpose of the divertor coil device provided in this embodiment is to provide an experimental platform for studying divertor physics on a linear device. Based on vacuum-insulated excitation lead technology, the topological structure of the divertor configuration is generated by applying an external current. For the first time in a linear device, a complete divertor configuration including the last closed magnetic surface, fractal lines, X-point, and divertor foot points is constructed. This provides an efficient and precise small-scale experimental platform for subsequent research on divertor physics: 1. plasma-target interaction; 2. the influence of the divertor magnetic field structure on plasma transport; 3. plasma turbulence and coherent structure, etc.

[0058] One of the features of this embodiment is the divertor magnetic field configuration on the linear device: After the linear device generates a uniform magnetic field configuration with a length of 2.1m and a 0-2000 Gauss plateau, the poloidal field coil 2 is then turned on with a current of 600A. This adds a poloidal field to the uniform magnetic field, and the magnetic induction intensity of the poloidal field gradually decreases outward from the poloidal field coil 2, reaching approximately 0.1T in the vicinity of the poloidal field coil 2. Then, the divertor magnetic field coil is turned on with a current of 600A, generating a magnetic field configuration opposite to that of the poloidal field coil 2. The two configurations superimpose in the lower half of the device, creating a magnetic null point and forming the divertor magnetic field configuration. Simulation results show that the X-point of this divertor magnetic field configuration is located 120mm below the center of the main coil and 10mm to the right. The X-point configuration is similar to that of the X-point configuration on a tokamak device, exhibiting an asymmetrical structure. Turning on auxiliary coil 3 affects the configuration of the divertor magnetic field, adjusting the length, width, and position of point X. There are three typical activation modes for auxiliary coil 3: 1. Both left and right auxiliary coils 3 are activated with a rated current of 200A. This compresses the width of point X, making the magnetic field lines near point X denser and elongating the overall magnetic field configuration. 2. Only the left auxiliary coil 3 is activated with a current of 200A. This strengthens the magnetic field on the left, shifting point X 25mm to the right. The shape of point X is also affected, with greater curvature of the magnetic field lines on the left and less curvature on the right. 3. Only the right auxiliary coil 3 is activated with a current of 200A. This strengthens the magnetic field on the right, shifting point X 25mm to the left. The shape of point X is affected in the opposite way to mode 2. The above scenarios represent the maximum magnetic field variations in the design. To achieve the specific magnetic field configuration, the poloidal field coil 2, divertor coil 4, and auxiliary coil 3 can be adjusted as needed to obtain the target experimental parameters.

[0059] The second feature of this embodiment is the structural design of the poloidal field coil 2: a wire is used to traverse the vacuum chamber laterally in the linear device to add a poloidal field to the uniform magnetic field structure of the linear device itself. With this design, the device can generate a magnetic field structure similar to that in a tokamak device, which then interacts with the magnetic field generated by the divertor coil 4 to produce a divertor magnetic field configuration, realizing the physical design of generating a divertor configuration magnetic field on the linear device. The poloidal field coil 2 is designed as a structure with six coils distributed at the six vertices of a regular hexagon. The outer side of the hexagon can be approximated as generating a near-circular poloidal magnetic field line mechanism, while a six-level magnetic field is formed inside the hexagon, creating a weak magnetic field region at the center, facilitating the generation and injection of non-contact plasma sources such as helical wave plasma sources and microwave sources. The injected plasma can bypass the poloidal field coil 2 along the six-pole magnetic field lines to generate an equivalent "core" plasma.

[0060] The third feature of this embodiment is the wide range of adjustable parameters achieved through the structural design of the divertor coil 4 and auxiliary coil 3. The divertor coil 4 consists of two sets of parallel, co-directional coils laid at the bottom of the vacuum chamber. This widens the area below point X, making the divertor configuration more reasonable, reserving a wider space for the target plate design, and reducing the current parameters of a single wire. The auxiliary coil 3 is designed near point X of the divertor configuration under rated current, using a two-coil design with a distance of 100mm between them. This allows for adjustment of the shape of the divertor magnetic field and the left-right position of point X without affecting the plasma exiting from the main magnetic field region.

[0061] The fourth feature of this implementation method is the vacuum coil insulation and protection design: Unlike typical linear devices, this design uses small-diameter coils that traverse the vacuum chamber to minimize their impact on the plasma during the experiment. The coils are centrally water-cooled to ensure long-term steady-state operation of the high-current conductors in a vacuum-insulated environment. Insulation between the coils and the plasma is achieved through alumina ceramic spraying technology. The surrounding magnetic field generated when the coils are turned on protects the conductors from plasma sputtering and overheating.

[0062] in, Figure 2-3 This diagram shows a cross-sectional view and front view of the divertor coil assembly. The five outer coils are the main magnetic field coils 5, each with a cross-section of 156*260mm and an aperture g(mm) = 640. The wire used in the coils has a cross-section of 12*12 / Φ8mm, with a 1mm insulation layer. Each coil has N = 240 turns. The maximum designed current of the coils is Imax(A) = 600A. The main magnetic field coils 5 are housed in a vacuum chamber. The poloidal field coils 2, divertor coils 4, and auxiliary coils 3 pass parallel to each other within the vacuum chamber. The structure of the two side walls of the vacuum chamber and the loop sections of the poloidal field coils 2, divertor coils 4, and auxiliary coils 3 are not shown in the diagram.

[0063] The outer region is a side view of the main magnetic field coil 5, with an outer diameter of 1160 mm and an inner diameter of 640 mm. The coil is clad in a 20 mm thick DT4 yoke and is tightly fitted to the vacuum chamber. The chamber has an outer diameter of 640 mm and an inner diameter of 540 mm. Figure b is a cross-sectional view of the chamber interior. The six circular areas in the upper right of the figure represent the poloidal field coil 2. Each coil consists of six sets of wires, symmetrically distributed on a circle with a radius of 85 mm. The angle between any two adjacent sets of coils is 60°. The center of the circle is located 100 mm above the center of the main magnetic field and 40 mm to the right. The divertor coil design uses 20 turns per coil, with a maximum current Imax (…). A=600, single coil diameter 20mm. The two circular areas at the bottom of the chamber are the divertor magnetic field coils, consisting of two sets of wires. The coils are close to the bottom of the chamber, symmetrically distributed 30mm on each side of the perpendicular bisector. Each divertor coil uses 30 turns, designed for a maximum current Imax ( A =600, single coil diameter 24mm. The two circular areas located between the poloidal field coil 2 and the divertor coil 4 constitute the auxiliary coil 3, consisting of two sets of wires. The lateral spacing between the two sets of wires is 100mm, the lateral distance from the center of each wire is 10mm, and the longitudinal distance from the center is 120mm. A single auxiliary coil 3 is designed with 10 turns, and the maximum designed current Imax is... A =300, single coil diameter 15mm. When the coil is turned on, the poloidal field coil 2 and divertor coil 4 are directed inwards, while the auxiliary coil 3 is directed outwards. This generates an adjustable divertor magnetic field configuration.

[0064] The vacuum chamber is 3m long. The main parts of the poloidal field coil 2, divertor coil 4 and auxiliary coil 3 are located in the vacuum chamber. These three types of coils are parallel to each other and pass through the five sets of main magnetic field coils 5.

[0065] Figure 4 This is a diagram showing the magnetic field results of the divertor coil device. The magnetic field direction on the cross-section is as follows: [Diagram showing the magnetic field direction on the cross-section of the divertor coil when the coil is turned on.] Figure 4 The two-thirds of the area in the figure is the main plasma region. In this region, the low magnetic induction intensity region inside the poloidal field coil 2 can be seen, and the outer part is a clear poloidal magnetic field configuration. The lower third of the region is the divertor configuration region, and the X point position can be clearly seen. The bottom open magnetic field line position is the divertor target plate. The plasma is first transported from inside the poloidal field coil 2 to the poloidal field region, and then reaches the divertor target plate after passing through the X point.

[0066] Figure 5 In the diagram, a and b represent the magnetic field results of the divertor under the adjustment of auxiliary coil 3. a indicates that the left auxiliary coil 3 is turned on, and b indicates that the right auxiliary coil 3 is turned on. With the help of auxiliary coil 3, the poloidal field region does not change much, while the position and shape of point X change significantly. The simulation results show that the adjustable range of point X on both sides is -20mm to 35mm. At the point where the position change is the greatest, point X approaches auxiliary coil 3, reaching the physical design limit.

[0067] Figure 6 This is a cross-sectional schematic diagram of an alternative to the divertor coil assembly; as an alternative, a single poloidal field coil 2 is used. Figure 2 The difference is that the poloidal field coil 2 is located 140mm above the center of the main magnetic field coil 5 and 40mm to the right. The main part of the coil is located inside the vacuum chamber, traversing the five sets of main magnetic field coils 5. The coil circuit is 3m away from the chamber. The coil design uses a 120-turn coil, with a maximum current Imax (A =600, single coil diameter 50mm.

[0068] Figure 7 The magnetic field result diagram of the alternative divertor coil device is shown. With the coil activated, the divertor magnetic field is as follows: the direction of the magnetic field on the cross-section is... Figure 7 The upper two-thirds of the area is the main plasma region, and the poloidal magnetic field configuration outside the coil is still obvious. The lower third of the region is the divertor configuration region, and the X point can be clearly seen. The bottom open magnetic field line position is the divertor target plate. The plasma is first transported from inside the poloidal field coil 2 to the poloidal field region, and then reaches the divertor target plate after passing through the X point.

[0069] Figure 8 Figures a and b show the results of the divertor magnetic field under the adjustment of the auxiliary coil 3 of the alternative device. Figure a shows the left auxiliary coil 3 being turned on, and figure b shows the right auxiliary coil 3 being turned on. With the help of the auxiliary coil 3, the poloidal field region does not change much, but the position and shape of point X change significantly. The simulation results show that the adjustable range of point X on the left and right sides is -10mm to 30mm. At the point where the position change is the greatest, point X approaches the auxiliary coil 3, reaching the physical design limit.

[0070] Implementation Method 10: Combination Figure 2-3 This embodiment further defines the filter coil device provided in Embodiment Nine. There are five main magnetic field coils 5, which are arranged in parallel to each other. The length of the vacuum chamber 1, the poloidal field coil 2, the auxiliary coil 3, and the diverting coil along the axial direction is greater than the distance between the beginning and end of the main magnetic field coil 5 along the axial direction.

[0071] The above description of several specific embodiments further details the technical solution provided by the present invention, in order to make the advantages and benefits of the technical solution provided by the present invention clearer. However, the above-described specific embodiments are not intended to limit the present invention. Any modifications and improvements to the present invention, combinations of embodiments, and equivalent substitutions based on the spirit and principles of the present invention should be included within the protection scope of the present invention.

Claims

1. A bias coil module, characterized by, The module comprises a poloidal field coil (2), an auxiliary coil (3), a divertor coil (4) and a vacuum chamber (1); The vacuum chamber (1) is a cylindrical structure, and the poloidal field coil (2), the auxiliary coil (3) and the divertor coil (4) are located inside the cylindrical structure; The poloidal field coil (2) is used to provide a uniform magnetic field along the axis direction of the cylindrical structure when conducting; The divertor coil (4) is used to provide a magnetic field in the opposite direction of the uniform magnetic field when conducting, and the magnetic field and the uniform magnetic field superimpose to generate a magnetic zero point; The auxiliary coil (3) is used to provide a magnetic field for adjusting the divertor magnetic field configuration when conducting.

2. The bias coil module of claim 1, wherein, The vacuum chamber (1) is a cylindrical structure.

3. The bias coil module of claim 1, wherein, The poloidal field coil (2) comprises six groups of wires, and the six groups of wires are parallel to the axis of the cylindrical structure; a plane perpendicular to the axis is defined as a projection plane, and a virtual image of the six groups of wires projected on the projection plane is six vertices of a regular hexagon.

4. The bias coil module of claim 3, wherein, The six groups of wires are single-turn coils.

5. The bias coil module of claim 1, wherein, The divertor coil (4) comprises two groups of wires, and the two groups of wires are parallel to the axis of the cylindrical structure.

6. The bias coil module of claim 5, wherein, The two groups of wires are single-turn coils.

7. The bias coil module of claim 1, wherein, The auxiliary coil (3) comprises two groups of wires, and the two groups of wires are parallel to the axis of the cylindrical structure.

8. The bias coil module of claim 7, wherein, The two groups of wires are single-turn coils.

9. A guard coil arrangement, characterized by The device comprises a main magnetic field coil (5) and a divertor coil module, the divertor coil module is the divertor coil module of claim 1, and the main magnetic field coil (5) is sleeved outside the vacuum chamber (1).

10. A guard coil arrangement according to claim 9, characterised in that The main magnetic field coil (5) has five and is arranged in parallel with each other, and the length of the vacuum chamber (1), the poloidal field coil (2), the auxiliary coil (3) and the divertor coil (4) along the axis direction is greater than the distance between the head and the tail of the main magnetic field coil (5) along the axis direction.

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