Magnetic inertial fusion device and method for accelerating compressed field reversed configuration plasma

Abstract

This invention relates to the field of controlled nuclear fusion technology, providing a magnetic inertial fusion device and method for accelerating and compressing field-inverted plasma. The device is an integrated linear structure, comprising, from both ends to the middle, a divertor chamber, a field-inverted plasma formation section, a linear acceleration section, a conical tube pre-compression section, and a collision-fusion and magnetic compression region. FRC plasma is formed in the formation section, its axial velocity is increased in the acceleration section, and then pre-compression and stability are improved in the conical tube pre-compression section. After the plasmas at both ends collide and fuse in the middle region, they are magnetically compressed by electromagnetic pulses to reach a medium density (~10²⁴ m⁻³) and fusion temperature, triggering the fusion reaction. The above process can be repeated, the stability of the fusion plasma can be effectively controlled throughout the process, the pulse power heating of the plasma is highly efficient, and the plasma temperature and density can be controlled to simultaneously reach the required fusion conditions; providing an optimal solution for the commercialization of fusion energy.

Description

Technical Field

[0001] This invention relates to the field of controlled nuclear fusion technology and provides a magnetic inertial fusion device and method for accelerating compressed field anti-configuration plasma. Background Technology

[0002] Over the past seventy years, research on controlled nuclear fusion has mainly focused on two directions: one is low-density (10²) nuclear fusion. 0 Magnetic confinement devices using (m⁻³) plasma, such as tokamak and stellarator, are extremely large due to their low density, resulting in very high construction costs and development cycles of several decades. The second type is inertial confinement fusion using ultra-high density (10³¹m⁻³) plasma, such as hydrogen bombs and laser fusion. This type of fusion requires extremely high heating power and relies on extreme means such as atomic bombs and high-energy laser arrays. It not only suffers from high costs and long development cycles, but also has the technical drawback of difficulty in reproducing the fusion process.

[0003] Given the above difficulties, the industry has proposed the magneto-inertial fusion (MINS) approach. MINS utilizes the excellent confinement properties of magnetic fields on plasma, combined with high-power heating methods, theoretically enabling miniaturization of fusion devices and reducing their cost. Current MINS research only began a little over a decade ago. Some MINS methods employ compressed tokamak plasma, but the low β characteristic of tokamak plasma means that the vast majority (>99%) of the compression power is consumed by the magnetic field, resulting in very low efficiency in increasing plasma temperature and density. Another approach uses Z-pinch, but this method suffers from poor confinement properties, requiring nanosecond (ns) level pulse power to compress the plasma, which is technically challenging, and the energy coupling efficiency between the plasma and the electromagnetic pulse system is low.

[0004] Field inverse configuration (FRC) plasmas have very high β values, approaching 100%, and possess closed magnetic field lines, resulting in excellent confinement performance. Therefore, microsecond (μs) level pulsed power systems can be used to heat the plasma, significantly reducing technical difficulty and greatly improving the coupling efficiency between the plasma and the pulsed power system, reaching over 20%. Thus, the magnetoinertial fusion route using compressed field inverse configuration plasmas becomes the optimal choice.

[0005] In the prior art, various magnetic inertial fusion devices based on FRC have been disclosed. For example, Chinese patent document CN105185417A (publication date December 23, 2015, invention title "Magnetic Plasma Fusion Ignition Device and Inertial Magnetic Confinement Fusion Method Thereof") discloses a device that achieves fusion ignition by forming a reverse-field configured plasma cluster, head-to-head collision fusion, and sleeve implosion compression. This technology mainly adopts the solid sleeve implosion compression method, which has a complex structure and is destructive each time it runs, making it difficult to achieve repeatable high-frequency operation; in addition, the solid sleeve absorbs most of the compression power during implosion, resulting in very low compression heating efficiency for the plasma and extremely high requirements for compression power.

[0006] Chinese patent document CN106981317A (publication date July 25, 2017, invention title "Magnetized Plasma Fusion Ignition Device and Local Rapid Acceleration Heating Ignition Method Thereof") proposes a fusion ignition scheme employing a multi-stage acceleration system and a compression jet system. This scheme, relying solely on acceleration jetting, cannot significantly increase plasma density; the unilateral asymmetric design cannot effectively control the plasma to maintain axial combustion.

[0007] Chinese patent document CN112397206B (authorization announcement date May 9, 2023, invention title "A Field Anti-Plasma Magnetic Compression Device and Method") proposes a cascaded magnetic compression scheme. This scheme first expands the plasma after its formation, and then performs magnetic compression. This design results in a large magnetic compression coil radius and a large space required to fill the compression magnetic field (the space between the coil and the plasma boundary), leading to low compression efficiency and high energy storage requirements for the power system. Furthermore, the plasma elongation ratio decreases during high-ratio magnetic compression, causing plasma instability. In addition, this scheme lacks a method for controlling the ratio of plasma temperature to density, which may result in the temperature and density after compression not simultaneously reaching the parameters required for fusion.

[0008] Chinese patent document CN214476430U (authorization announcement date October 22, 2021, invention title "An Axial Compression Fusion Device Based on Field Inverse Plasma") discloses a scheme for axial compression using a high-speed plasma cluster generator array. However, the axial compression of this scheme reduces the elongation ratio, which easily leads to instability of the FRC plasma; moreover, the high-speed plasma cluster has a low density, resulting in low compression efficiency for the FRC plasma, and the density cannot be effectively increased.

[0009] Furthermore, US Patent No. 11049620B2 (granted on June 29, 2021, entitled "METHOD AND APPARATUS FOR THE GENERATION, HEATING AND / OR COMPRESSION OF PLASMOIDS AND / OR RECOVERY OF ENERGY THEREFROM") discloses a method for achieving fusion by forming a field-inverse configuration (FRC) plasma mass, accelerating its collision, and magnetically compressing it. This patent further describes a technical solution for directly recovering electrical energy through coils during plasma expansion. This solution has achieved a fusion-related plasma temperature of 150 million degrees Celsius, representing a relatively advanced design for a magneto-inertial fusion device. However, this scheme is followed by a conical section immediately after the plasma formation section. While plasma compression can be achieved within the conical section, plasma acceleration is difficult to achieve. This compact structure lacks the means to control the temperature and density ratio, which may lead to the plasma, after compression, not reaching the temperature and density required for fusion simultaneously. Furthermore, the conical section uses fast pulse compression, which cannot use metal wall materials that would hinder the rapid penetration of electromagnetic pulses. The compression process is similar to magnetic compression, which leads to a decrease in the plasma elongation ratio. Therefore, it is also impossible to effectively control the stability of the plasma during the compression process.

[0010] Therefore, it is necessary to develop a compact structure that enables repeatable high-frequency operation, maintains plasma stability, efficiently utilizes pulsed power, and allows for simultaneous control of plasma temperature and density to achieve the desired fusion conditions, with a density reaching ~10. 24 m -3 The systematic design optimization of magnetic inertial fusion devices at the scale of [number] remains a technical problem that urgently needs to be solved in this field. Summary of the Invention

[0011] To address the aforementioned shortcomings, the present invention aims to provide a magnetic inertial fusion device and method for accelerating compressed field reverse-configuration plasma. The purpose is to solve the technical problems in existing FRC fusion devices, such as poor plasma stability, low plasma density, inability to effectively control the plasma temperature and density ratio, low plasma heating efficiency, and lack of an integrated linear fusion structure.

[0012] In general, the device of the present invention uses a linear device to form field-inverted plasma;

[0013] The plasma is axially accelerated using a linear device to achieve optimized temperature and density after collision and fusion.

[0014] By utilizing the pre-compressed and accelerated plasma through a metal conical tube, some of its kinetic energy is converted into thermal energy, and the elongation ratio is increased, thereby improving stability and reducing losses during the collision and fusion process.

[0015] The symmetry of the device is used to enable plasma collision and fusion to form optimized target plasma;

[0016] The target plasma is then compressed using electromagnetic pulses to achieve a medium density (~10²). 4 The process involves achieving a state of m⁻³ and a high temperature (greater than 100 million degrees) required for fusion, ultimately resulting in a stable fusion reaction and releasing fusion energy for commercial power generation.

[0017] The above process involves the generation, acceleration, pre-compression, collision fusion, and magnetic compression of FRC plasma in sequence; the entire process can be repeated, thereby increasing the power output of fusion power generation.

[0018] The field-inverted plasma is an elongated toroidal plasma with a plasma current in the shape of a circumferential solenoid. The magnetic field generated in the core is opposite to the magnetic field generated by the external coil, and the two ends are magnetically reconnected to form a closed magnetic field line structure, which has good plasma confinement performance.

[0019] The FRC magnetic inertial fusion device of the present invention is an integrated linear structure, comprising, from both ends to the middle, the following components along the axial direction:

[0020] The divertor chamber, the field-reverse plasma formation section, the acceleration section, the conical tube pre-compression section, the collision fusion and magnetic compression zone are all coaxially arranged, and the whole device is mounted on a parallel guide rail base through a support structure. The sections are detachably connected by flanges.

[0021] Structurally, the device includes two or more divertor chambers for injecting fusion fuel gas;

[0022] Connected to the output of the divertor chamber, it is used to ionize fusion fuel gas to form plasma and construct FRC plasma in a field-reversible plasma forming section.

[0023] Connected to the output of the in-field reverse-position plasma formation section, it is an acceleration section used to provide an acceleration path for the FRC plasma;

[0024] Connected to the output end of the acceleration section, the inner diameter of which gradually decreases along the direction of plasma movement is used to compress the FRC plasma that has passed through the acceleration section.

[0025] Collision fusion and magnetic compression region used for collision fusion to form target plasma and for magnetic compression of target plasma;

[0026] It also includes: several sets of coils disposed outside the above-mentioned cavities of the magnetic inertial fusion device. Several sets of coils disposed outside each of the above-mentioned tube sections means that they are disposed relatively outside the internal vacuum cavities. They can be disposed individually outside the tube sections or disposed as an integral part of the tube sections.

[0027] Furthermore, this device has a linear structure, with the collision fusion and magnetic compression region located in the middle.

[0028] The pre-compression section, acceleration section, field-reversed plasma formation section, and divertor chamber are coaxially arranged outward from both ends of the collision fusion and magnetic compression zone.

[0029] Furthermore, the divertor chamber is equipped with several interfaces for connecting vacuum, gas filling, pre-ionization, diagnostic, and power generation equipment.

[0030] Furthermore, several sets of the coils are also disposed outside the field-reverse plasma formation section, acceleration section, pre-compression section, and collision fusion and magnetic compression zone.

[0031] Furthermore, the feature is that several sets of coils are electrically connected to an external control system, which controls the sequential discharge of the several sets of coils to drive the FRC plasma to move along the direction of motion.

[0032] Furthermore, several sets of coils outside the collision fusion and magnetic compression zone can apply electromagnetic pulses to the interior of the collision fusion and magnetic compression zone.

[0033] Furthermore, the pre-compression section adopts a tapered tube structure.

[0034] Furthermore, the pre-compression section is made of metal.

[0035] Meanwhile, the present invention also provides a method for accelerating magnetic inertial fusion of compressed field anti-configuration plasma, comprising the following steps:

[0036] S1. Fusion fuel gas is blown into the source end of each forming segment chamber of the multi-segment chamber;

[0037] S2. By applying coupled electromagnetic pulses through coils outside the chamber, the fusion fuel gas in the source end of each chamber is ionized to construct FRC plasma;

[0038] S3. Multiple groups of FRC plasmas are continuously accelerated forward in their respective chambers by the action of several external coils.

[0039] After the S4 and FRC plasmas are accelerated to the initial kinetic energy required for subsequent fusion, they continue to move to the pre-compression section where the inner diameter of their respective chambers is reduced, and undergo further compression under the constraint of the physical form of the pre-compression section.

[0040] S5 and FRC plasmas travel to the end of each pre-compression section;

[0041] The ends of each pre-compression section are interconnected to form a collision fusion region, and each group of FRC plasmas collide and fuse in the collision fusion region to form target plasma;

[0042] S6. Within the collision fusion zone, the target plasma is compressed using electromagnetic pulses to achieve the density and high temperature required for fusion, thereby generating a stable fusion reaction and releasing fusion energy.

[0043] Therefore, the beneficial effects of the present invention are as follows:

[0044] This invention achieves stable fusion of medium-density plasma through an integrated linear structure design of "divertor chamber - formation section - acceleration section - conical tube pre-compression section - collision fusion and magnetic compression zone" combined with the efficient application of electromagnetic pulse technology. Compared with existing technologies, it has the following significant advantages:

[0045] The device features a simple linear design, is reusable, and significantly reduces construction costs (approximately 1 / 100th of those of magnetic confinement fusion devices). The entire device is mounted on a parallel guide rail base, with each section connected by flanges. When maintaining specific components, they can be moved along the guide rails to separate them, enabling rapid replacement and greatly reducing the device's maintenance and operating costs.

[0046] The entire process of plasma formation, acceleration, and compression utilizes highly efficient electromagnetic pulse technology, resulting in high energy utilization efficiency and effectively reducing the cost per kilowatt-hour of fusion power generation, thus laying the foundation for the commercialization of fusion energy.

[0047] The device has low time and cost for design and construction, and does not require complex, large-scale structures or extreme heating equipment, which can greatly accelerate the research and development of nuclear fusion technology.

[0048] The combined design of a dedicated linear acceleration section and a conical tube pre-compression section can reasonably adjust the temperature and density of the plasma after collision and fusion, so that the subsequent magnetic compression energy can simultaneously obtain ideal fusion temperature and density parameters, thereby improving the stability of the fusion reaction.

[0049] Compared with traditional dielectric material pre-compression structures, the tapered tube pre-compression section can generate equivalent wall compression for plasma, effectively improving plasma stability parameters. At the same time, the plasma stability during the compression process can be further improved by optimizing the taper, linearity, and inner wall structure, ensuring the reliability of the magnetic compression process.

[0050] The linear device structure can be adapted to magnetohydrodynamic direct power generation technology, and the coil-related pulse power supply can be connected to an energy recovery system to further improve the overall efficiency of fusion energy power generation.

[0051] The acceleration section can be flexibly added according to actual fusion needs to obtain the required FRC plasma velocity. The device has strong adaptability and optimizability, which facilitates subsequent technology iteration.

[0052] The tapered tube pre-compresses the plasma to a smaller radius, reducing the radius of the magnetic compression coil, which can greatly improve the efficiency of the pulse power used for compression.

[0053] The device is reusable, laying the foundation for stable commercial applications.

[0054] This invention provides a method for operating at medium density (~10²) 4 A magnetic inertial fusion device with an accelerated and compressed field anti-configuration plasma under m⁻³ plasma conditions, simple structure, low construction cost, short R&D cycle, convenient operation and maintenance, high stability of fusion plasma, and high heating efficiency is the preferred option for the commercial application of fusion energy. Attached Figure Description

[0055] Figure 1 A schematic diagram of the field-inverted plasma structure;

[0056] Figure 2 It is a three-dimensional structure of the FRC magnetic inertial fusion device;

[0057] Figure 3 This is a diagram illustrating the internal structure and fusion principle of the FRC magnetic inertial fusion device.

[0058] Figure 4 This is a schematic diagram of the plasma motion process in the FRC magnetic inertial fusion device.

[0059] In the diagram:

[0060] 101-Fluid conservator; 102-Open magnetic field lines; 103-Closed magnetic field lines; 104-Plasma current; 105-Plasma configuration; 200-FRC plasma; 201-Divertor chamber; 202-Field inverse configuration plasma formation section; 203-Acceleration section; 204-Pre-compression section; 205-Collision fusion and magnetic compression region; 206-Coil. Detailed Implementation

[0061] The technical solutions of the present invention will be clearly and completely described below with reference to the accompanying drawings of the embodiments of the present invention. Obviously, the described embodiments are only some embodiments of the present invention, and not all embodiments.

[0062] It should be noted that, in the description of this invention, unless otherwise stated, "a plurality of" means two or more; the terms "upper," "lower," "left," "right," "inner," "outer," "front end," "rear end," "head," "tail," etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings, and are only for the convenience of describing this invention and simplifying the description, and do not 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 this invention. Furthermore, the terms "first," "second," "third," etc., are used for descriptive purposes only and should not be construed as indicating or implying relative importance.

[0063] Furthermore, in the description of this invention, unless otherwise explicitly specified and limited, the terms "connected" and "linked" should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral connection; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium. Those skilled in the art can understand the specific meaning of the above terms in this invention based on the specific circumstances.

[0064] To make the objectives, technical solutions, and advantages of this invention clearer, the invention will be further described in detail below with reference to the accompanying drawings. It should be understood that the specific embodiments described herein are merely illustrative and not intended to limit the invention.

[0065] See appendix Figure 1-3 As shown, the purpose of this invention is to provide a magnetic inertial fusion device for accelerating compressed field anti-configuration plasma. The device is an integrated linear structure, comprising, from both ends to the middle, the following components along the axial direction:

[0066] The divertor chamber 201, the field-reversed plasma formation section 202, the acceleration section 203, the pre-compression section 204, and the collision fusion and magnetic compression zone 205 are all coaxially arranged, and the entire device is mounted on a parallel guide rail base via a support structure. The sections are detachably connected by flanges. The specific structure and working principle are as follows:

[0067] Divertor chamber 201: Symmetrically arranged at both ends of the device, it serves as an interface for auxiliary equipment such as vacuum, gas filling, pre-ionization, diagnostic and power generation equipment, providing basic environmental conditions for plasma formation.

[0068] Field-inverse plasma formation section 202: Located adjacent to the divertor chamber 201, it ionizes the fusion fuel gas blown inside the chamber using electromagnetic pulses coupled to coil 206 to form plasma and construct a field-inverse plasma configuration (FRC). By controlling the sequential discharge of coil 206, the formed FRC plasma 200 is pushed axially towards the center of the device, achieving initial axial movement of the plasma. Coil 206 provides the electromagnetic pulse power.

[0069] Acceleration Section 203: Located adjacent to the field-reversed plasma formation section 202, it is a dedicated linear acceleration structure used to further increase the axial velocity of the plasma pushed from the formation section, so that the plasma can obtain the initial kinetic energy required for subsequent fusion and optimize the compressed plasma target parameters.

[0070] Pre-compression section 204: Employing a tapered tube structure, pre-compression section 204 is preferably made of metal and is positioned adjacent to acceleration section 203. The inner diameter of pre-compression section 204 gradually decreases along the plasma motion direction, compressing the FRC plasma 200 from the acceleration section to a smaller radius, facilitating improved efficiency during subsequent magnetic compression. Simultaneously, it converts the plasma's kinetic energy into thermal energy, increasing the plasma's temperature, density, and elongation ratio, thereby enhancing plasma stability.

[0071] Collision Fusion and Magnetic Compression Region 205: Located in the center of the device, this is the core region for the collision fusion and final magnetic compression of the plasmas at both ends. After acceleration and pre-compression, the FRC plasmas 200 at both ends of the collision fusion and magnetic compression region 205 collide and fuse in this region to form target plasma, achieving a high initial temperature and density. Then, electromagnetic pulses are used to achieve magnetic compression of the target plasma, ultimately bringing it to a moderate density (~10²). 4 (m⁻³) and the high-temperature nuclear fusion conditions required for fusion trigger the fusion reaction.

[0072] Example 1

[0073] This embodiment is combined with the appendix Figure 2 and attached Figure 3 As shown, specific embodiments of the present invention will be described in detail.

[0074] This embodiment provides a specific example of a magnetic inertial fusion device for accelerating and compressing field-inverted plasma, comprising, along the axial direction from both ends to the middle, a divertor chamber 201, a field-inverted plasma formation section 202, an acceleration section 203, a pre-compression section 204, and a collision fusion and magnetic compression zone 205; each section is coaxially arranged and detachably connected by a flange structure; the entire device is fixed to a parallel guide rail base by a welded support structure, the guide rail base being made of high-strength alloy material and possessing good load-bearing and mobility performance.

[0075] The divertor chamber 201 is connected to external vacuum equipment and gas filling equipment. The vacuum equipment evacuates the entire device to achieve the ultra-high vacuum environment requirements of the fusion device. Then, the gas filling equipment blows deuterium-tritium or other fusion fuel gases into the formation section, and at the same time, the pre-ionization equipment completes the preliminary pre-ionization of the gas to prepare for plasma formation.

[0076] The plasma formation and initial propulsion stage then begins. In this stage, the FRC coil of the field inversion plasma formation section 202 is coupled with an electromagnetic pulse to completely ionize the pre-ionized fusion fuel gas, forming field inversion (FRC) plasma. The sequential discharge of each coil 206 is controlled by a programmable controller, causing the formed FRC plasma 200 to move axially toward the acceleration section in the middle of the device. The discharge timing is precisely controlled according to the plasma formation speed and the propulsion distance.

[0077] For details, please see the appendix. Figure 1 As shown, the structure of the field-reversed plasma inside the flux conservator 101 includes core structures such as open magnetic field lines 102, a field-reversed region with closed magnetic field lines 103, and a plasma configuration 105 with plasma current 104.

[0078] The plasma then enters the axial acceleration and propulsion stage. After entering the acceleration section 203, the coil 206 of the acceleration section releases a directional electromagnetic pulse, generating an axial thrust on the plasma and increasing its axial velocity to a preset value. In this embodiment, the accelerated plasma axial velocity meets the kinetic energy requirements for subsequent pre-compression and collision fusion. The number of acceleration sections 203 can be increased according to the velocity requirements; in this embodiment, one acceleration section is sufficient to achieve the preset acceleration effect. A key function of the acceleration section 203 is its ability to regulate the ratio of target plasma temperature and density, ensuring that both parameters reach predetermined values ​​that meet the fusion conditions after magnetic compression.

[0079] The plasma then enters the plasma pre-compression stage. After being accelerated by the acceleration section 203, the plasma enters the pre-compression section 204 made of metal. The metal tapered tube is made of conductor material, and its taper is designed according to the density and temperature requirements of plasma pre-compression. The plasma moves in the tapered tube in the direction of narrowing inner diameter to achieve radial pre-compression. Kinetic energy is converted into thermal energy, and the density, temperature and elongation ratio of the plasma are increased, thus enhancing its stability.

[0080] The process then proceeds to the collision fusion and magnetic compression stage. The pre-compressed plasmas at both ends collide in the collision fusion and magnetic compression zone in the middle of the device. The collision velocity is reduced by the pre-compression of the conical tube to minimize losses, resulting in the formation of a uniform target plasma with a high preset initial temperature and density. Subsequently, coil 206 in the magnetic compression zone releases a high-intensity electromagnetic pulse to rapidly magnetically compress the target plasma, bringing its density to a moderate level (~10²). 4 When the temperature reaches the threshold required for fusion (m⁻³), a stable fusion reaction is triggered.

[0081] For energy recovery and device maintenance in the fusion process: the energy released by the fusion reaction is converted into electrical energy through a magnetohydrodynamic direct power generation device connected to the coil. The electromagnetic energy used to accelerate and compress the plasma that is not completely consumed can also be recovered and reused through the coil-related system. If maintenance or replacement of parts is required after the device is in operation, the flange connection of the corresponding section can be loosened, and the parts can be moved along the parallel guide rail base to achieve rapid separation and hoisting replacement of the parts. After maintenance is completed, the flange can be reconnected to restore the device to operation.

[0082] The device in this implementation case can achieve a stable and repeatable fusion reaction. Its construction cost is less than 1 / 100 of that of a traditional tokamak device. The research and development cycle is significantly shortened, and the operation and maintenance costs are low, which fully meets the technical and cost requirements for commercial fusion power generation.

[0083] Of course, the present invention may have other various embodiments. Without departing from the spirit and essence of the present invention, those skilled in the art can make various corresponding changes and modifications according to the present invention, but these corresponding changes and modifications should all fall within the protection scope of the appended claims.

Claims

1. A magnetic inertial fusion device and method for accelerating compressed field anti-configuration plasma, characterized in that, include: Two or more divertor chambers (201) for injecting fusion fuel gas. A field-reversible plasma forming section (202) is connected to the output of the divertor chamber (201) for ionizing fusion fuel gas to form plasma and constructing FRC plasma (200). An acceleration section (203) is connected to the output of the field-inverted plasma formation section (202) to provide an acceleration stroke for the FRC plasma (200). A pre-compression section (204) connected to the output end of the acceleration section (203) with an inner diameter that gradually decreases along the plasma movement direction is used to compress the FRC plasma (200) after passing through the acceleration section. Collision fusion and magnetic compression region (205) for collision fusion to form target plasma and magnetic compression of target plasma. It also includes: several sets of coils (206) disposed outside the upper cavity of the magnetic inertial fusion device.

2. The magnetic inertial fusion device for accelerating compressed field reverse-configuration plasma according to claim 1, characterized in that, This device has a linear structure, and the collision fusion and magnetic compression region (205) is located in the middle. The collision fusion and magnetic compression zone (205) has the pre-compression section (204), acceleration section (203), field inversion plasma formation section (202), and divertor chamber (201) arranged coaxially outward from both ends.

3. The magnetic inertial fusion device for accelerating compressed field reverse-configuration plasma according to claim 1, characterized in that, The divertor chamber (201) is provided with several interfaces for connecting vacuum, gas filling, pre-ionization, diagnostic and power generation equipment.

4. The magnetic inertial fusion device for accelerating compressed field reverse-configuration plasma according to claim 1, characterized in that, Several sets of coils (206) are also disposed outside the field-reverse plasma forming section (202), the acceleration section (203), the pre-compression section (204), and the collision fusion and magnetic compression zone (205).

5. The magnetic inertial fusion device for accelerating compressed field anti-configuration plasma according to any one of claims 1 or 4, characterized in that, Several sets of coils (206) are electrically connected to an external control system. The control system is used to control the sequential discharge of several sets of coils (206) to drive the FRC plasma (200) to move along the direction of motion.

6. The magnetic inertial fusion device for accelerating compressed field reverse-configuration plasma according to claim 4, characterized in that, Several sets of coils (206) outside the collision fusion and magnetic compression zone (205) can apply electromagnetic pulses to the interior of the collision fusion and magnetic compression zone (205).

7. The magnetic inertial fusion device for accelerating compressed field reverse-configuration plasma according to claim 1, characterized in that, The pre-compression section (204) adopts a tapered tube structure.

8. The magnetic inertial fusion device for accelerating compressed field reverse-configuration plasma according to claim 1, characterized in that, The pre-compression section (204) is made of metal.

9. A method for accelerating magnetic inertial fusion of compressed field inverse-configuration plasma, characterized in that, Includes the following steps: S1. Fusion fuel gas is blown into the source end of each forming segment chamber of the multi-segment chamber; S2. By applying coupled electromagnetic pulses through coils outside the chamber, the fusion fuel gas in the source end of each chamber is ionized to construct FRC plasma; S3. Multiple groups of FRC plasmas are continuously accelerated forward in their respective chambers by the action of several external coils. After the S4 and FRC plasmas are accelerated to the initial kinetic energy required for subsequent fusion, they continue to move to the pre-compression tube section with a reduced inner diameter in their respective chambers, where they undergo further compression under the constraints of the physical shape of the pre-compression tube section. S5 and FRC plasmas travel to the ends of each pre-compression tube section; The ends of each pre-compression tube section are interconnected to form a collision fusion zone, and each group of FRC plasmas collide and fuse in the collision fusion zone to form target plasma; S6. Within the collision fusion zone, the target plasma is compressed using electromagnetic pulses to achieve the density and high temperature required for fusion, thereby generating a stable fusion reaction and releasing fusion energy.

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