A fusion ignition system based on compact toroidal magnetic field compression technique

Abstract

The application discloses a fusion ignition system based on compact toroidal magnetic theta-pinch compression technology and belongs to the technical field of nuclear fusion energy. The system generates high-speed and high-density compact toroidal plasma by a symmetric coaxial gun, injects the plasma into a vacuum chamber, triggers cascading theta pinch through a single-turn ring array, enhances the compact toroidal angular current and its own magnetic field, combines with a superconducting steady-state magnetic theta-pinch to form a moving magnetic mirror structure, suppresses the tilt instability and pushes it to the central collision area. After the collision and fusion of the compact toroidal plasma on both sides, the central magnetic mirror keeps the coil group to provide slow theta pinch to maintain the fusion condition, realizes plasma density>10 23 / m 3 , ion temperature>15 keV, energy confinement time>2 ms, and meets the Lawson criterion. The system can be switched to a magnetized target fusion mode, impacts a magnetized target through secondary compact toroidal collision to realize axial compression and magnetic reconnection fusion. A power generation module adopts a cladding and electromagnetic induction double-mode energy recovery. The technology has the advantages of compact structure, low cost and convenient maintenance, and provides a new way for commercial fusion power generation.

Description

TECHNICAL FIELD

[0001] The application belongs to the technical field of nuclear fusion energy, and particularly relates to a fusion ignition system based on a compact toroidal magnetic theta-pinch compression technology, which is suitable for controllable nuclear fusion energy development. BACKGROUND

[0002] Deuterium-tritium fusion ignition needs to meet the Lawson criterion of high density, high ion temperature and long energy confinement time, that is, deuterium-tritium fusion ignition needs fusion triple product However, existing experimental devices still face challenges when meeting the above conditions at the same time. Controllable nuclear fusion research in the past mainly has two ways, magnetic confinement and inertial confinement. Magnetic confinement fusion has a relatively high energy confinement time, such as the energy confinement time of the current tokamak device can reach seconds, but the plasma density is usually low, which is 5 orders of magnitude lower than the particle number density in air. Inertial confinement fusion can obtain very high plasma density through compression of the target pellet, which is 6 orders of magnitude higher than the particle number density in air, but its energy confinement time is very short, usually in nanoseconds. At present, both ways are still far from commercial fusion energy.

[0003] Magnetized plasma collision is a technology for rapidly heating plasma, which can effectively convert magnetic energy into plasma thermal energy and even improve the confinement performance through magnetic reconnection. The TAE company in the United States adopts the field reversed configuration, merges two field reversed (FRC) plasmas into one field reversed plasma through mutual collision, and then applies a neutral beam to improve the plasma temperature and confinement performance, with a duration of several milliseconds. Helion Energy in the United States has obtained a plasma temperature of 9keV, that is, 110 million degrees Celsius, through cascading compression of field reversed plasmas. Recently, it announced a power purchase agreement with Microsoft, and will connect the world's first commercial nuclear fusion power generator to the power grid before 2028 and deliver it to Microsoft.

[0004] Magnetized target fusion (MTF) is a fusion energy concept that combines the features of magnetic confinement fusion (MCF) and inertial confinement fusion (ICF). Similar to the magnetic confinement method, the fusion fuel is heated into plasma and the lower density plasma is confined by a magnetic field. At the same time, by rapidly compressing the target material, the density and temperature of the plasma can be significantly improved, thereby triggering the fusion reaction. The magnetized target technology combines the advantages of magnetic confinement and inertial compression, and opens up a new path for the development of fusion energy. The domestic Xingguang of Xinghua Energy uses field reversed configuration and inertial compression to produce FRC magnetized target plasma, and then uses four cascading field reversed plasma to collide and compress the FRC magnetized target, which directly converts the kinetic energy and part of the magnetic energy of the plasma into heat energy. Its structure is compact and the cost is controllable. The MagLIF technology proposed by the Sandia National Laboratory in the United States first pre-installs an axial magnetic field to magnetize the fuel and suppress electron heat conduction loss. Then the deuterium-tritium fuel is heated to ~100 eV by laser. Finally, the fuel is imploded by high-power pulsed current to compress the fuel to a high-temperature and high-density state (also known as Z pinch), so that the fusion energy gain Q is close to 1. The General Fusion company in Canada injects a deuterium-tritium spherical plasma into a liquid metal liner, and then uses a high-power piston to compress it inward, thereby increasing the transient pressure and density of the plasma and reducing the dependence on extreme high temperature to achieve the conditions for fusion reaction. At the same time, the fusion reaction will produce neutrons, which can react with lithium in the liquid metal to generate more tritium. It is planned to achieve a fusion condition of more than 100 million degrees Celsius before 2025, and to reach the breakeven point in 2026, and to provide commercial fusion energy to the power grid in the early to mid-2030s. It can be seen that the magnetized target fusion combines the advantages of long energy confinement time in magnetic confinement and high density in inertial confinement, and has become a new emerging fusion approach, showing strong market competitiveness.

[0005] For magnetized plasma, the energy confinement time is usually between the Bohm ) and the gyro-Bohm ), and the plasma specific pressure , which represents the ratio between the magnetic pressure and the thermal pressure , so the fusion triple product can be written as

[0006] In recent years, the gradual maturity of high-temperature superconducting technology brings new opportunities for magnetic confinement fusion. Because the specific pressure of tokamak and stellarator is low (1-5%), leading to large volume, a lot of superconducting materials are needed, so the cost of the device is high. At the same time, the three-dimensional coil of the stellarator and the D-shaped coil of the tokamak are limited by material stress, and the magnetic field strength at the fusion reaction site is limited. In order to maximize the advantages of high-temperature superconducting strong magnetic field, the fusion should be made to occur at the center of the circular cross-section solenoid, and the radius of the high-temperature superconducting coil should be reduced.

[0007] In the field of strong magnetic field generation technology, the current mainstream scheme mainly relies on two technical routes: steady-state strong magnetic field system based on high-temperature superconducting material, and pulse strong magnetic field system based on low-inductance copper coil structure. High-temperature superconducting coil has the characteristics of high critical current density and negligible joule heat loss, and can maintain a steady-state magnetic field of tens of tesla level at 4.2K low temperature environment; while the pulse strong magnetic field system can realize a transient magnetic field strength of more than 100T through the use of optimized coil inductance design and high-power pulse power supply (peak current up to MA level, pulse width μs-ms level). By constructing a composite magnetic field generation system, the total field strength is significantly improved. This dual-mode magnetic field coordination mechanism not only breaks through the physical limitation of traditional single field source, realizes the complementary advantages of steady-state magnetic field stability and transient magnetic field strength, and opens up a technology path with engineering scalability for fusion reactor engineering design.

[0008] For the topology of magnetized plasma, all open magnetic field line schemes cannot achieve Lawson criterion due to terminal loss resulting in too short energy confinement time. At present, three closed magnetic configurations are the most promising to achieve fusion energy: tokamak (including spherical torus, the highest technology maturity), stellarator (has steady-state advantage, but is the most difficult to manufacture), and compact toroid (simplest structure and lowest cost). The coaxial gun is a flexible tool in nuclear fusion research, which generates high-speed and high-density compact toroids using electromagnetic force. The compact toroid generated by the coaxial gun has both poloidal and toroidal magnetic fields, and is more stable than field-reversed plasma; more importantly, it can achieve very high plasma specific pressure .

[0009] The application applies the coaxial gun to generate compact toroids, pulse coil group cascade theta pinch, high-temperature superconducting strong field adiabatic compression, and magnetic mirror to suppress compact toroid instability, so as to compress the compact toroids to the magnetic cone center for collision fusion to achieve the ignition condition of fusion. This scheme introduces high-temperature superconducting strong magnetic field into the field-reversed magnetic compression technology, and combines the compact toroid of the coaxial gun to maximize the strong magnetic field and high specific pressure to the current technical level. SUMMARY

[0010] The application provides a fusion ignition system based on a compact ring magnetic cone impulsive compression technology, two high-speed and high-density compact rings are generated by coaxial guns, compact ring cascade theta pinch is completed by axially distributed pulse coils, and the compact rings are restrained by a moving magnetic mirror formed by the pulse coils and a superconducting hybrid magnet, the magnetic mirror is suppressed to push the compact rings into the center of the magnetic cone formed by the superconducting hybrid magnet, and the fusion is completed, the magnetic mirror is further maintained and strengthened by a magnetic mirror maintaining coil group, the deuterium-tritium fusion ignition is realized, and the defects of high cost and low efficiency of the traditional technology are overcome.

[0011] The system can also run in a magnetized target fusion mode, the compact rings formed by the fusion are disappeared, and the compact rings are emitted from two sides again, compressed by cascade compression, and hit the central compact ring magnetized target to perform axial compression, and new compact rings are formed by magnetic reconnection fusion, so that a higher fusion triple product parameter is achieved.

[0012] The system is named as MAGIC (Magnetic-cone Adiabatic Gradient-force Impulsive Compressor) in English.

[0013] The technical scheme of the application is as follows:

[0014] A fusion ignition system based on a compact ring magnetic cone impulsive compression technology, comprising

[0015] Symmetrically distributed coaxial guns are used to generate high-speed and high-density compact rings.

[0016] A vacuum chamber, the axial center of which is a plasma collision area, adopts quartz except that the vacuum chamber wall of the collision area is made of non-magnetic stainless steel, and tungsten tiles are arranged at both ends of the vacuum chamber and the inner wall of the collision area, and a tungsten-copper water cooling structure is adopted.

[0017] Conventional pulse coils are symmetrically arranged along the axial direction of the vacuum chamber, are composed of single-turn niobium-copper coils and N50 non-magnetic stainless steel, and are sequentially triggered to generate transient magnetic fields to push the compact rings, and the pulse coils close to the center participate in the maintenance of the fusion reaction.

[0018] A magnetic mirror maintaining coil group is arranged below the superconducting hybrid magnet to generate a tens-of-millisecond confinement field to maintain the fusion reaction.

[0019] A superconducting hybrid magnet is arranged in the collision area and is composed of a high-temperature superconducting magnet and a low-temperature superconducting magnet to generate a steady-state magnetic cone confinement field.

[0020] A tritium breeding blanket surrounds the vacuum chamber and the coaxial gun ports, all the blanket angular directions are insulated and separated to facilitate the penetration of the magnetic field, and an interleaved structure is adopted to avoid neutron leakage.

[0021] Low-temperature superconducting reverse magnet is symmetrically arranged at the periphery of the coaxial gun outlet and the vacuum chamber connection, and the magnetic field intensity at the coaxial gun outlet is adjusted.

[0022] The power generation module is realized by double-mode power generation of neutron moderated heat energy and electromagnetic induction magnetic energy recovery.

[0023] In the above technical solution, the coaxial guns are symmetrically distributed at the two ends of the vacuum chamber, and are used for generating high-speed and high-density compact rings; the working gas is a mixture of deuterium and tritium; the plasma is formed by high-voltage pulse ionization of the gas; and the Lorentz force is used for acceleration.

[0024] In the above technical solution, the vacuum chamber is a lying circular cross-section long cylinder, the axial center of the vacuum chamber is a plasma collision area, the vacuum chamber at the collision position is a non-magnetic stainless steel, the angular direction has an insulating partition, and the inner wall is covered with tungsten tiles; the passages of the compact rings on the two sides of the vacuum chamber in the axial direction of the magnetic field line are composed of quartz tubes or silicon carbide fiber reinforced ceramic matrix composites. The tungsten tiles are arranged on the inner walls of the two ends of the vacuum chamber and the collision area to avoid damage to the vacuum chamber wall by high-energy particles along the magnetic field line. The boronized wall treatment can be used to reduce metal impurities in the plasma.

[0025] In the above technical solution, the plurality of pulse coils are symmetrically arranged along the axial direction of the vacuum chamber, the pulse coils are sequentially triggered to generate transient magnetic fields, the transient magnetic fields and the strong magnetic field generated by the superconducting hybrid magnet jointly form a moving magnetic mirror structure to capture and constrain the compact rings, and the compact rings are quickly and stably pushed to the magnetic cone center region; the pulse coils are composed of a plurality of single-turn coils, and the material is niobium copper or copper chromium alloy, and the outside is welded with N50 non-magnetic stainless steel to strengthen the mechanical strength.

[0026] In the above technical solution, the superconducting hybrid magnet is arranged in the center tube collision area, the superconducting hybrid magnet generates a stable strong magnetic field at the axial center position of the vacuum chamber, the magnetic field lines extend to the two sides of the collision area to form a magnetic cone constraint field, the magnetic cone gradually compresses the compact rings in the process of the compact rings moving to the collision area, increases the density and temperature of the compact rings, the compact rings on the left and right sides are coaxially collided with each other, the pulse coils close to the center, the magnetic mirror maintaining coil group close to the coils and the superconducting hybrid magnet jointly form a strengthened magnetic mirror to constrain the fusion reaction of tens of milliseconds, and the superconducting hybrid magnet is arranged in parallel from inside to outside by high-temperature superconducting and low-temperature superconducting.

[0027] In the above technical solution, the magnetic mirror maintaining coil group is arranged below the superconducting hybrid magnet and surrounds the tritium breeding blanket in the center region, the magnetic mirror maintaining coil group is composed of a plurality of wide multi-turn coils, and the magnetic mirror maintaining coil group is circumscribed by N50 non-magnetic stainless steel.

[0028] In the technical scheme, the tritium breeding blanket surrounds the whole vacuum chamber and part of ports of the coaxial gun, and the vacuum chamber is also separated from the superconducting hybrid magnet by the tritium breeding blanket for neutron moderation and radiation shielding, all the tritium breeding blankets are angularly separated and insulated to facilitate the penetration of the magnetic field, and the tritium breeding blanket adopts the staggered structure to avoid neutron leakage.

[0029] In the technical scheme, the low-temperature superconducting reverse magnet is arranged on both sides of the superconducting hybrid magnet, is located at the joint of the coaxial gun port and the vacuum chamber, and can generate a magnetic field opposite to the superconducting hybrid magnet to control the magnetic field size at the outlet of the coaxial gun.

[0030] In the technical scheme, in addition to the neutron moderation and absorption in the tritium breeding blanket to convert into heat energy for power generation, the power generation module can also directly generate power through electromagnetic induction. After the fusion reaction occurs, the thermal pressure of the plasma increases, and the volume expands, and the plasma preferentially escapes from the magnetic mirror constraint in the axial direction. The magnetic fluid passes through the coil array channel, and the electromagnetic induction causes the coil current to change, directly converting into electric energy, and then the energy is recovered through an insulated gate bipolar transistor. Meanwhile, after the alpha particles generated by the fusion escape through the loss cone of the magnetic mirror, the particles move axially along the magnetic field line to form a current, and through electromagnetic induction, the energy is fed back to the capacitor through a single-turn ring, thereby recovering the energy.

[0031] Beneficial effects:

[0032] The application provides a fusion ignition system based on a compact ring magnetic cone pulse compression technology, and high-speed and high-density compact rings are injected into a vacuum chamber through coaxial gun technology. Subsequently, a cascade pulse magnetic field excited by a pulse coil group is coupled with a stable magnetic cone generated by a superconducting hybrid magnet to jointly construct a dynamic magnetic mirror structure. The compact rings are effectively captured and constrained by the magnetic mirror, undergo a cascade theta pinch compression and heating process, and are driven by the magnetic mirror force to move to a central collision area, and finally collide with and fuse with another compact ring which also undergoes the process. The pulse coil close to the center on the two sides of the magnetic cone center, the magnetic mirror holding coil group and the superconducting hybrid magnet jointly generate a tens-of-millisecond-level strengthened magnetic mirror structure to constrain high-temperature and high-density compact rings and realize deuterium-tritium fusion ignition. In the pulse coil and the superconducting magnetic cone field, the plasma follows the principle of magnetic flux conservation, the volume of the compact ring is inversely proportional to the magnetic field, and the density and the magnetic field are positively correlated, so that the plasma density can be increased to , the ion temperature reaches , the energy confinement time is , and the fusion triple product required for deuterium-tritium fusion ignition is met . The magnetic field of the compact ring superimposed on the background magnetic field of 30T can reach more than 50T, and the magnetic pressure is sufficient to balance the thermal pressure of the fusion plasma In such a strong magnetic field, some plasma turbulence and instabilities are not easy to occur, for example, due to Alfven velocity In a strong magnetic field, some high-energy particle excited Alfven eigenmodes are not easy to be excited.

[0033] In addition, due to the compression and guiding of the magnetic cone to the center position of the vacuum chamber, the fusion position is far away from the wall of the vacuum chamber, which reduces the interaction of the plasma with the wall and the damage of the high-energy particles to the wall. At the same time, due to the short energizing time of the pulse coil, the magnetic energy stored in the inductance of the coil can be recycled through the circuit, so the energy consumption of the coil system is low. The service life of components such as niobium copper coil, insulation and vacuum chamber under neutron irradiation is more than 3 years, and as a consumable, the replacement cost is low. Moreover, the need for an auxiliary heating system is a significant advantage, and the auxiliary heating system of the tokamak and the stellarator not only has high cost but also usually has poor operation reliability. The modules of the main components of the device are modularly designed, simple in structure, compact, and convenient for daily maintenance and disassembly and replacement. The volume and cost of the entire fusion reactor are only 1 / 100 of the tokamak and the stellarator fusion reactor, which significantly improves the economic competitiveness of fusion energy and reduces the cost of electricity, and has great potential value. Therefore, the present application has novelty, creativity and practicality. BRIEF DESCRIPTION OF DRAWINGS

[0034] Figure 1 It is a transverse vertical sectional view of a compact ring magnetic cone pulse compressor;

[0035] Figure 2 It is the current waveform of the microsecond pulse coil, the central pulse coil and the magnetic mirror maintaining coil group;

[0036] Figure 3 It is a structure diagram of 1x10 in the wiring terminal of single-turn ring and 3x10;

[0037] Figure 4 It is a spatial distribution diagram of the magnetic field generated by the magnetic mirror maintaining coil group in the axial direction;

[0038] Figure 5 It is a spatial distribution diagram of the steady-state magnetic field generated by the superconducting hybrid magnet in the axial direction;

[0039] Figure 6 It is an axial distribution diagram of the hybrid magnetic field in the vacuum chamber at different times;

[0040] Figure 7 It is a structure diagram of the magnetic mirror capturing the compact ring magnetic field;

[0041] Figure 8 It is a parameterized simulation result diagram of COMSOL particle tracking;

[0042] Figure 9This is a simulation result diagram showing the variation of fusion burning fraction with time under different constraint time constants.

[0043] In the picture:

[0044] 1: Coaxial gun; 2: Vacuum chamber; 3: Conventional pulse coil; 4: Pulse coil near the center; 5: Superconducting hybrid magnet; 6: Magnetic mirror holding coil assembly; 7: Low-temperature superconducting reverse magnet; 8: Tritium breeder blanket; 9: Gas injection port; 10: Single-turn coil; 11: N50 non-magnetic stainless steel; 12: Power generation module. DETAILED DESCRIPTION

[0045] The following will clearly and completely describe the technical solutions in the embodiments of the present invention in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are only part of the embodiments of the present invention, rather than all the embodiments. Based on the embodiments of the present invention, all other embodiments obtained by ordinary technicians in this field without creative work are within the scope of protection of the present invention.

[0046] Example

[0047] like Figure 1 As shown, this embodiment proposes a fusion ignition system based on compact ring magnetic cone pulse compression technology. A coaxial gun generates a high-speed compact ring. The pulse coil assembly utilizes the cascaded theta pinch effect and couples with the magnetic cone of a superconducting hybrid magnet to collaboratively confine, compress, and collide the compact ring, achieving deuterium-tritium fusion ignition. Furthermore, dual-mode power generation is achieved through neutron-moderated thermal power generation and electromagnetic induction magnetic energy recovery. The system comprises a coaxial gun 1, a pulse coil assembly (including a conventional pulse coil 3 and a pulse coil 4 near the center), a magnetic mirror holding coil assembly 6, a superconducting hybrid magnet 5, a low-temperature superconducting reverse magnet 7, a vacuum chamber 2, a tritium breeder blanket 8, and a water cooling system.

[0048] The coaxial gun 1 is symmetrically distributed at both ends of the vacuum chamber 2, and forms plasma by ionizing the gas through high-voltage pulses, and uses the Lorentz force to generate high-speed (40-400 km / s), high-density (≈1×10 22 ) compact ring, the repetitive pulse frequency can reach up to 50Hz, the upper end of the coaxial gun 1 is provided with a fuel injection port 9, the fuel gas is a mixed fuel of deuterium and tritium accounting for 50% each, and the caliber of the coaxial gun 1 can be set to 10-30cm according to actual needs;

[0049] The vacuum chamber 2 is arranged in the center of the whole device, the overall axial length of the vacuum chamber is 8 m, the outer diameter is 38 cm, and the wall thickness of the vacuum chamber is 2 cm. The wall of the whole vacuum chamber 2 is made of quartz material except for the collision area, the axial center of the vacuum chamber 2 is the plasma collision area, the wall of the collision position of the vacuum chamber is made of non-magnetic stainless steel, the inner wall is covered with tungsten tile, the tungsten copper water cooling structure is adopted, there is an insulating partition in the angular direction, and the electromagnetic shielding is avoided. The strong magnetic field of 20T limits the expansion of the plasma across the magnetic field lines, so as to weaken the interaction between the plasma and the wall. An important advantage of using magnetic cone compression instead of conical conductor wall compression is that the compressed plasma group is far away from the wall of the device, especially after the fusion of the plasma group, the volume of the plasma group will expand, so that the interaction between the plasma and the wall can be reduced, the impurity radiation can be reduced, and the service life of the internal components of the vacuum chamber can be prolonged.

[0050] The inner wall of the two end faces of the cylindrical vacuum chamber at the outlet position of the coaxial gun 1 on both sides of the vacuum chamber 2 is made of tungsten tile, and a tungsten copper water cooling structure is adopted to withstand the interaction of the particles escaping along the magnetic field lines. A circle of slits is arranged at the edge of the two end faces of the cylindrical vacuum chamber as a gas extraction port, which is similar to the structure of the divertor of the tokamak, and is connected with a low-temperature pump or an adsorption pump and the like to form a gas extraction system, so as to discharge fusion products and unreacted fusion fuel gas, and form a fuel circulation;

[0051] The conventional pulse coil 3 has 26 coils and is arranged symmetrically along the axial direction of the vacuum chamber 2. The material of the conventional pulse coil 3 can be changed according to actual requirements. For example, niobium-copper alloy with high yield strength suitable for high mechanical stress environment can be preferred, and copper-chromium alloy with excellent anti-radiation performance can also be selected. The reason why the single-turn ring pulse coil is preferred to be made of niobium-copper alloy is mainly that the niobium-copper alloy has relatively high yield strength (which can be more than 800 MPa), has relatively strong fatigue resistance and relatively long service life under repeated pulse operation conditions, and has relatively low resistivity when the content of niobium is less than 1%. However, the anti-neutron radiation performance of the niobium-copper alloy is not as good as that of the copper-chromium alloy, and the yield strength of the copper-chromium alloy is relatively low (about 500-700 MPa). If the conventional pulse coil 3 is made of copper-chromium alloy, it is estimated that fatigue cracks will appear after about 10 4 -10 5 times of pulses, and the cycle life of the coil can be improved by developing niobium-copper nanocrystalline alloy in the future. The outer side of each pulse coil is welded with N50 non-magnetic stainless steel 11 to strengthen the mechanical strength. Since the current passing through the coil is too short, the temperature rise of the coil can be ignored.

[0052] The conventional pulse coil 3 and the pulse coil 4 close to the center are triggered in turn to generate a transient magnetic field, and the strong magnetic field generated by the superconducting hybrid magnet 5 can be regarded as a magnetic mirror structure moving in the axial direction. The current rise time constant of the conventional pulse coil 3 is about 2 microseconds, and the current decrease time constant is about 50 microseconds. The coil current of the conventional pulse coil 3 gradually decreases from both ends to the middle. linear variation; the current rise time in the pulse coil 4 near the center is about 2 microseconds, and the current fall time constant is about 1 millisecond, and the current of all the coils is .

[0053] In the strong magnetic field, the time of the instantaneous change of the magnetic field is far greater than the gyration period of the particles, the magnetic moment conservation condition is met, and the square of the vertical direction velocity is proportional to the magnetic field The fast change of the magnetic field generated by the single-turn pulse coil group realizes the energy transfer through the non-equilibrium interaction of the electromagnetic field and the particles, the change of the magnetic field generates an induced electric field, the particles are rapidly adiabatically compressed, the vertical velocity of the particles is increased, and the magnetic energy is changed into the energy of the particles. The vertical pressure and the magnetic field strength are in a square relationship in the rapid adiabatic magnetic compression, that is, the vertical thermal pressure and the magnetic pressure are synchronously increased. At the same time, since the compact torus before the magnetic compression is a high , the plasma with a density of can be obtained after compression. In the initial compact torus, even if the initial directed kinetic energy of the particles is completely converted into thermal energy, the temperature is increased by less than 1 keV, and therefore the directed kinetic energy is not the main energy supply source.

[0054] The most critical thing of the linear device is to suppress the loss in the axial direction. In the present application, the combination of the self-confinement of the compact torus and the dynamic magnetic mirror realizes the double suppression of the axial transport. On the one hand, the compact torus has a closed magnetic field topology, which can effectively reduce the terminal loss of the particles in the axial direction. On the other hand, the dynamic magnetic mirror is used to confine the compact torus in the axial direction, and the magnetic mirror further reduces the axial loss of the particles. At the same time, since the plasma temperature at the compression starting point is very low at the coaxial gun outlet, the axial velocity is very low. During the movement of the compact torus, there is no effective acceleration mechanism for the compact torus in the axial direction, and the collision energy exchange time in the parallel direction and the vertical direction is much longer than the compression time, so the axial direction will always remain low temperature and low speed, and therefore a shallow magnetic mirror can well confine the compact torus. Since the parallel magnetic field direction of the electron has a much greater thermal conductivity than the ion, and the collision energy exchange time of the electron and the ion is also much longer than the compression time, a higher ion temperature can be obtained, and the ion temperature in the magnetic mirror is maintained to be much higher than the electron temperature, and the lower electron temperature can reduce the bremsstrahlung and cyclotron radiation energy loss. If the state can be stably maintained, as long as the required fusion triple product is achieved, deuterium-deuterium fusion (including helium-3) and proton-boron fusion are also feasible, which means that the fusion fuel is inexhaustible, and the radioactivity safety problem of tritium is avoided.

[0055] The preferred choice for conventional pulse coil groups and pulse coils close to the center is a single-turn coil 10 of niobium-copper alloy containing 1% niobium, with an inner diameter of 40 cm, an axial height of 15 cm, and a radial thickness of 7 cm. Taking into account the current skin effect of microsecond pulse current in a single-turn ring, it is possible to consider silver plating on the surface of the single-turn ring to reduce its surface resistance. Multiple strands of insulated thin wire can be connected in parallel (Litz wire structure) to disperse the high-frequency current path. The total surface area of ​​multiple strands of wire is larger, which can weaken the skin effect and reduce the overall inductance by parallel connection. It is planned to use a 20-meter-long coaxial cable to connect the capacitor to power the coil. The outer diameter of the cable is 4 cm and the total resistance is 20 meters. , total cable inductance The resistance and inductance of a single-turn loop are much smaller than those of the loop, so the resistance and inductance of a single-turn loop can be ignored. There are two types according to the different power circuits. The conventional 26 coils are powered by low-inductance fast-discharge capacitors, and the voltage across the capacitors is about 100kV. , through a resistor in series R~0.5 , the current rise time constant of the RLC circuit , fall time constant ,like Figure 2 As shown in (a) in the figure. The four pulse coils 4 near the center have too high currents, with a total current of 6mA, and the maintenance time needs to be in the order of milliseconds. Therefore, 30 power supplies are connected in parallel to power a single-turn loop. Each power supply is 200kA, and the connectors are designed in a 3×10 array, as shown in the figure. Figure 3 As shown in (a) and (b) in the figure. Ultra-high voltage power capacitors can be used for power supply. , the current rise time of the RLC circuit , fall time constant , the discharge waveform is as follows Figure 2 The repetition frequency of the entire system depends on the capacitor charging time. Theoretically, the maximum repetition frequency can reach 50Hz.

[0056] In the compact toroid, the Lorentz force of the poloidal current and the background magnetic field is the core confinement force to maintain the plasma equilibrium. This electromagnetic force effectively counteracts two main expansion effects through the magneto-hydrodynamic (MHD) equilibrium mechanism: the radial expansion force driven by the thermal pressure gradient and the magnetic tension generated by the interaction of the poloidal current and the self-generated toroidal magnetic field. The pulsed coil system has a dual mechanism in the confinement of the electromagnetic field: on the one hand, the transient magnetic field of the coil and the two magnetic fields generated by the superconducting hybrid magnet are coupled to form a dynamic magnetic mirror confinement configuration, which can capture the compact toroid and rely on the magnetic mirror force to suppress the tilt instability of the compact toroid, thereby stably pushing the compact toroid from the low magnetic field region of the magnetic cone to the high magnetic field region; on the other hand, when the compact toroid sequentially passes through the pulsed coil array, the poloidal current in the compact toroid is continuously enhanced through the cascading theta pinch effect, continuously compressing and stabilizing the compact toroid structure. At the same time, due to the short pulse time of the pulsed coil array, the rotational instability can be avoided to prevent rupture.

[0057] The two magnetic mirror maintaining coil groups 6 are arranged outside the four near-center pulsed coils 4 to compensate for the magnetic field drop of the four near-center pulsed coils 4 during current drop. Each magnetic mirror maintaining coil group 6 has five parallel sub-coils, with an inner diameter of 70 cm, an outer diameter of 142 cm, and a height of 50 cm. Each sub-coil is a multi-turn coil with 360 turns, and the coil current is synchronously supplied by five power supplies, with inductance and resistance The loop resistance is configured to 17.6 by connecting the resistors in series. The coil driving voltage is 10 kV, and the discharge current waveform has a rise time of 100 ns and a flat top of more than 10 ms. When the coil current of the magnetic mirror maintaining coil group reaches the peak value, the magnetic field distribution is as shown in Figure 4 , which, after coupling with the background magnetic field as shown in Figure 5 , forms a quasi-steady magnetic mirror that can confine the compact toroid. The capacitor energy storage for powering the pulsed coil can be changed to superconducting inductance energy storage, which can greatly reduce the volume of the power supply and can be applied to spacecraft, aircraft carriers and other occasions requiring miniaturization in the future.

[0058] The superconducting hybrid magnet 5 is arranged in the central collision region, and the superconducting hybrid magnet 5 is arranged in parallel from inside to outside by high-temperature superconductors and low-temperature superconductors. The superconducting hybrid magnet 5 generates a stable strong magnetic field at the axial center of the vacuum chamber 2, and the magnetic field lines extend to both sides of the collision region to form a magnetic cone structure, and the maximum magnetic field strength at the peak of the magnetic cone can reach 20T, as shown in Figure 5 . The compact toroid will be gradually compressed during the process of being pushed to the center by the transient magnetic field generated by the pulsed coil, and when the magnetic compression time is shorter than the magnetic diffusion time , the magnetic freezing condition is met, and the magnetic flux is conserved Assuming the length of the compact toroid along the magnetic field line is constant, the volume shrinks as the magnetic field increases , and according to the conservation of particle number , the density increases as the magnetic field increases At the peak of the magnetic cusp, the inner diameter of the compact toroid is compressed to 1 / 20 of the exit diameter of the coaxial gun, so that the compact toroid is far away from the wall of the vacuum chamber, reducing the interaction between the plasma and the wall, and also increasing the density of the compact toroid to According to the conservation of magnetic moment, the perpendicular temperature increases as the magnetic field increases , and the perpendicular pressure increases as the square of the magnetic field In this process, the external magnetic pressure does work, and the electromagnetic field energy is transferred to the plasma, while compression and heating are achieved. After the coaxial collision of the compact toroids at both ends, the magnetic field undergoes magnetic reconnection, releasing a large amount of magnetic energy into heat energy. This process not only enhances the confinement ability of the total magnetic field, but also further heats the plasma. In fact, the magnetic field at the fusion site of the collision is the superposition of the steady-state magnetic field of the superconducting hybrid magnet 5, the magnetic field generated by the four closest pulsed coils, the magnetic mirror holding coil group 6, and the remaining magnetic field after the magnetic reconnection of the compact toroids. The hybrid magnetic field collectively confines the fusion reaction for more than 5 times the energy confinement time. The parameter range of the compact toroids at the exit of the coaxial gun, the parameter range of the compact toroids in the central collision region, and the parameter variation multiple are shown in the following table.

[0059] Table 1 Compact toroid parameter range and parameter variation multiple

[0060]

[0061] The system can also operate in a magnetized target fusion mode. Before the high-beta compact toroid formed by the initial collision and fusion decays and disappears, secondary compact toroids are injected from both sides simultaneously again, and through cascading compression, they collide with the central compact toroid magnetized target, axially compressing it, and through magnetic reconnection fusion, a new compact toroid is formed to achieve higher fusion triple product parameters.

[0062] The heating scheme of the pulsed coil array + high temperature superconducting magnetic toroid has many unique innovations. Compared with the plasma group generated by FRC, the compact toroid generated by the coaxial gun has a significantly enhanced angular magnetic field component, which has comparable strength characteristics with the polar magnetic field. This unique magnetic topology is conducive to the pulsed coil to induce stronger angular induced current in the compact toroid plasma through the magnetic flux compression effect. The compact toroid can be regarded as the moving secondary winding of the dynamic magnetic coupling transformer, and forms a spatiotemporally precise modulation electromagnetic induction coupling system with the primary winding composed of the pulsed coil array. When the compact toroid passes through the pulsed coil group along the axial direction, each primary unit is excited by the transient magnetic flux through time sequence control, producing a cascading theta pinch effect. The theta pinch of the compact toroid is similar to the poloidal field system of the tokamak, which generates poloidal magnetic flux penetration through fast rising current, induces electron current along the helical magnetic force line in the plasma toroid, and forms a radially inward self-contracting potential well through E×B drift; the guiding center motion of electrons in the strong helical magnetic field produces a nonlinear coupling between the paramagnetic poloidal current component and the diamagnetic angular (toroidal) current component, thereby producing a stronger angular (toroidal) magnetic field and a reverse axial magnetic field. When the compact toroid continuously passes through multiple levels of coils, the cascading theta pinch effect amplifies the angular (toroidal) current density step by step, and the magnetic shear layer formed by the self-consistent magnetic field and the background magnetic field can effectively suppress the tilt mode and tearing mode instability, achieving dynamic stability. The cascading theta pinch process can be analogized to a gyro acceleration model: when the compact toroid (analogous to a rotating gyro) advances along the magnetic axis, the arrayed pulsed coil array (analogous to an array of whip holders) applies directional energy injection when the compact toroid passes through each coil through precise coordinated control, continuously increasing the gyro energy. Compared with the central solenoid heating scheme of the tokamak, this energy deposition strategy not only breaks through the limitation of the volt-second number of a single coil, but also enables rapid compression and heating of the plasma by enhancing the magnetic field and current, resulting in a significant increase in plasma density and temperature within a sub-millisecond time, and ultimately achieving an extreme parameter operating state.

[0063] The tritium breeding blanket 8 covers the entire vacuum chamber 2 and part of the muzzle of the coaxial gun 1, and the coverage area of the blanket can reach more than 99.9%, which is easier to achieve self-sustaining of tritium; at the same time, the vacuum chamber 2 and the superconducting hybrid magnet 5 are also separated by the tritium breeding blanket 8, which mainly functions as neutron moderation and radiation shielding. All tritium breeding blankets 8 are provided with partitioning and insulation measures in the angular direction to promote magnetic field penetration. In addition, the tritium breeding blanket 8 adopts an interleaved structure design to effectively prevent neutron leakage;

[0064] The low-temperature superconducting reverse magnet 7 is arranged on both sides of the superconducting hybrid magnet 5, is located at the joint of the coaxial gun 1 port and the vacuum chamber 2, and can generate a magnetic field opposite to the superconducting hybrid magnet 5 to offset the static magnetic field generated by the superconducting hybrid magnet 5, so as to increase the magnetic field strength difference from the edge to the center, thereby achieving the function of controlling the magnetic field strength at the outlet of the coaxial gun 1, and avoiding the influence of the magnetic field on the normal work of the coaxial gun;

[0065] The power generation module 12 can only utilize the neutrons generated by fusion to slow down and absorb in the tritium breeding blanket to convert into heat energy for power generation, and can also directly generate power through electromagnetic induction. After the fusion reaction occurs, the thermal pressure of the plasma increases, the volume expands, and the plasma preferentially escapes from the magnetic mirror in the axial direction. The magnetic fluid passes through the coil array channel, and the electromagnetic induction causes the coil current to change (similar to the principle of electromagnetic braking), which is directly converted into electric energy. The energy is recovered through an IGBT (Insulated Gate Bipolar Transistor) switch circuit, and the theoretical recovery efficiency can reach >90%. Unlike traditional heat exchange systems and steam turbine power generation, the efficiency of the latter can only reach 35%. At the same time, after the alpha particles generated by fusion escape from the compact toroid and the magnetic mirror, the particles move axially along the magnetic field lines. In a 30T magnetic field, the cyclotron radius of the alpha particles is about 9mm, which determines the minimum inner diameter of the vacuum chamber. The collision slowing-down time is in the order of 100 microseconds, and the cyclotron radiation helps to slow down the alpha particles. The alpha particles that escape through the loss cone of the magnetic mirror form a current, which is fed back to the capacitor through electromagnetic induction. In the entire process, the single-turn loop pulse coil has a short energization time and extremely low resistance, resulting in little joule heat and low energy consumption. At the same time, most of the magnetic energy stored in the single-turn loop inductance can be recovered through an RLC series circuit to recharge the capacitor, further reducing the energy consumption of the coil system.

[0066] The simulation of the mixed magnetic field distribution at different times at the axis of the vacuum chamber 2 in a single ignition experiment is shown in Figure 6 At the initial time t=0 microseconds, only the steady-state magnetic cone generated by the superconducting hybrid magnet 5 exists. In the following 26 microseconds, each pulse coil is triggered in turn to generate a transient magnetic field. The transient magnetic field and the magnetic cone field together form a dynamic magnetic mirror structure to confine the compact toroid, as shown in Figure 7 The sequential triggering of the pulse coils changes the magnetic mirror structure into a moving magnetic mirror. In this process, the compact toroid is gradually compressed and steadily pushed into the collision region. At t=25.9631 microseconds, the two end compact toroids collide and fuse. Subsequently, the magnetic field generated by the magnetic mirror holding coil group 6 is gradually replaced by the magnetic field of the pulse coil close to the center, ensuring that the compact toroid burns steadily in the collision region until the fusion reaction ends.

[0067] Under given coil parameters, the trajectory of a single ion following a changing magnetic field was simulated. The particle tracking program was used to perform a parametric sweep of the rise time constant of the coil pulse current and the initial velocity of the compact ring. The sweep results are shown in Figure 2. Figure 8 As shown in the figure, red indicates that the compact ring can eventually reach the center of the magnetic field, while blue indicates that the compact ring cannot reach the center of the magnetic field. Simulation results show that the coil rise time constant is less than 40 μs, and the initial speed of the compact ring is greater than 130 km / s and less than 200 km / s, which is the safe operating range of the device.

[0068] Assume that after the compact ring collision, the ratio of deuterium to tritium in the plasma is 1:1 and the density reaches 10 23 per cubic meter, the temperature is 15keV, and according to the deuterium-tritium reaction cross section, the time constant of its fusion combustion reaction is about 40ms. Due to losses such as plasma diffusion, not all deuterium and tritium can undergo fusion reaction. The final reaction share of the fusion reaction is related to parameters such as the time constant of the fusion reaction and the particle confinement time of the compact ring. Figure 9 Figures (a), (b), and (c) simulate the temporal evolution of the burning fraction of the compact ring plasma under different particle confinement time constants under these plasma parameters. The simulations show that for a particle confinement time constant of 1 ms (10 ms), the ultimate burning fraction can reach 2.4% (20%), exceeding the estimated parameters for future fusion tokamaks.

[0069] This system is suitable for building small 100MW-class fusion reactors and can be flexibly deployed as a distributed energy unit, directly embedded in high-energy-consuming facilities such as AI computing centers and heavy industrial bases to achieve near-zero-loss energy supply. Alternatively, multiple fusion reactor units can form a gigawatt-class fusion power station, serving as a regional energy hub and providing continuous and stable power output. Combined with renewable energy sources such as wind power and photovoltaics, this distributed smart energy system effectively addresses the intermittent and fluctuating nature of wind and photovoltaic power generation due to weather and daytime conditions, creating a dual-track model of "local green electricity + remote nuclear fusion," improving overall energy efficiency and stability.

[0070] Its revolutionary breakthrough is particularly evident in the field of deep space propulsion: Due to its compact size and high fusion triple product, the reactor can utilize a deuterium-deuterium-helium-3 fusion scheme to reduce neutron flux, potentially allowing installation inside spacecraft, making interstellar travel possible. Furthermore, the system can be modified to an open-ended structure, using a magnetic nozzle to eject plasma slugs, directly forming a high-thrust, long-endurance deep space propulsion system.

[0071] If fusion parameters need to be improved in the future, the following methods can be used: 1. Increase the power of the coaxial gun to the MW level to increase the density, temperature and directional movement speed of the compact ring at the coaxial gun outlet; 2. Increase the magnetic field strength to increase the energy confinement time of the compact ring.

[0072] The above embodiment provides a fusion ignition system based on compact toroidal magnetic theta-pinch compression technology. The system uses coaxial guns 1 to generate high-density and high-speed initial compact toroids injected into a vacuum chamber. A conventional pulse coil and a pulse coil close to the center are sequentially energized to generate a cascading transient electromagnetic field, which is coupled with a stable background strong magnetic field generated by a superconducting hybrid magnet 5 to form a dynamic magnetic mirror structure. The compact toroids are rapidly and stably pushed to the magnetic theta-pinch center region. The cascading theta-pinch effect and the magnetic theta-pinch strong magnetic field are used to continuously compress the compact toroids, so that the compact toroid plasma obtains higher order density and energy. Finally, the compact toroids generated by the coaxial guns 1 at both ends collide with each other in the magnetic theta-pinch center collision region and fuse and undergo fusion. During the fusion process, the magnetic mirror holding coil group 6 maintains the magnetic field generated by the pulse coil to stabilize the magnetic mirror structure of the collision region until the compact toroid plasma burning ends. The combination of self-confinement of the compact toroids and the dynamic magnetic mirror realizes double inhibition of axial transport, and solves the problem of terminal loss of the linear device. The system can realize deuterium-tritium ignition at the present stage, and has the characteristics of simple structure, convenient maintenance and low cost.

[0073] Parts of the application not described in detail are known in the art.

[0074] Although the specific embodiments of the present application are described above, the technical solutions of the present application are further described in detail to facilitate the understanding of the present application by those skilled in the art. However, it should be clear that the present application is not limited to the scope of the specific embodiments, and any modification, replacement, etc. obvious changes made by those skilled in the art within the scope of the spirit and principles of the present application defined and determined by the appended claims should be included in the protection scope of the present application.

Claims

1. A compact toroid based fusion ignition system characterized by, The application relates to a fusion reactor. The application comprises: Symmetric coaxial guns (1) for generating high-speed high-density compact toroids; A vacuum chamber (2) with a plasma collision zone in the axial center, wherein the vacuum chamber wall of the collision zone is made of non-magnetic stainless steel, the vacuum chamber wall at other positions is made of quartz, and tungsten tiles are arranged on the inner walls of the two ends of the vacuum chamber and the central collision zone, and a tungsten-copper water cooling structure is adopted; Conventional pulse coils (3) are single-turn coils arranged symmetrically along the axial direction of the vacuum chamber, which are composed of single-turn coils (10) and N50 non-magnetic stainless steel (11) and sequentially triggered to generate transient magnetic fields, carry out theta pinch, form moving magnetic mirrors, capture and push compact toroids; The coil structure of the pulse coil (4) close to the center is the same as that of the conventional pulse coil (3), and the coil material is niobium-copper or copper-chromium alloy, which is used for maintaining the fusion reaction of the collision zone; A superconducting hybrid magnet (5) is arranged in the central collision zone and is composed of a high-temperature superconducting magnet and a low-temperature superconducting magnet, generates a stable magnetic conical confinement field, and the central magnetic field is as high as 20T; the magnetic conical field is used instead of a non-conductor wall to confine the high-temperature plasma, thereby avoiding the interaction between the high-temperature plasma and the wall; A magnetic mirror maintaining coil group (6) is designed as a multi-turn copper coil and is symmetrically arranged below the superconducting hybrid magnet (5) to generate a confinement field of tens of milliseconds to maintain the fusion reaction; A low-temperature superconducting reverse magnet (7) is symmetrically arranged outside the connection between the coaxial gun (1) outlet and the vacuum chamber (2) to adjust the magnetic field intensity at the coaxial gun (1) outlet; A tritium breeding blanket (8) surrounds the vacuum chamber (2) and the port of the coaxial gun (1), all the angular insulating partitions of the blanket are convenient for the magnetic field penetration, and the staggered structure is adopted to avoid neutron leakage; 2. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: The gas injection port (9) of the coaxial gun (1) injects deuterium-tritium mixed gas fuel, forms high-density Plasma compact torus; this compact torus has both angular and polar magnetic fields, the outlet speed can reach 40 to 400 kilometers per second, and the repetition frequency is not more than 50 Hz.

3. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: A power generation module (12) converts heat energy into electric energy by using the tritium breeding blanket to absorb neutron energy, recovers magnetic energy through electromagnetic induction principle, and realizes double-mode power generation of heat energy and magnetic energy.

4. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: Along the axial direction of the vacuum chamber (2), 30 single-turn ring pulse coils are arranged, 26 of which are conventional pulse coils (3), and the other 4 are pulse coils (4) close to the center, which are symmetrically distributed on both sides of the collision zone.

5. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: The axial length of the superconducting hybrid magnet (5) is 140 cm, the inner diameter is 160 cm, and a stable magnetic field of 20T can be generated in the collision zone.

6. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: The magnetic mirror maintaining coil group (6) generates a magnetic field of 20T, and the magnetic field generated by the superconducting hybrid magnet is superposed to strengthen and maintain the magnetic mirror for more than 10ms, and the total magnetic field is more than 40T.

7. A compact toroid based fusion ignition system according to claim 1, wherein: The power generation module (12) realizes efficient recovery of magnetic energy through the electromagnetic induction effect of the single-turn ring coil array and a switching circuit.

8. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: The axial length of the vacuum chamber (2) is 8 m, the outer diameter is 38 cm, and the vacuum chamber wall thickness is 2 cm; except for the collision zone, the vacuum chamber wall is made of quartz tube or silicon carbide fiber reinforced ceramic matrix composite and other vacuum compatible insulating materials, the vacuum chamber wall of the collision zone is made of non-magnetic stainless steel, angular insulating partitions, and tungsten tiles are arranged on the two ends of the vacuum chamber and the inside of the collision zone to avoid damage to the vacuum chamber wall caused by high-energy particle bombardment. The reverse magnetic field intensity generated by the low-temperature superconducting reverse magnet (7) is 50%-80% of the magnetic field intensity of the superconducting hybrid magnet (5).

9. A fusion ignition system based on compact toroid magnetic field line- tripling compression technique according to claim 1, characterized in that: The regular pulse coil (3) and the near-center pulse coil (4) are both single-turn loop coils, with an inner diameter of 40 cm, an axial height of 15 cm, and a radial thickness of 7 cm; the regular pulse coil (3) is powered by a fast discharge capacitor, with a current rise time of 2 μs, a fall time of 50 μs, and a current that increases from both ends to the core, and a current of 2-6 MA; the near-center pulse coil (4) is powered by an ultra-high voltage power capacitor, with a current rise time of 2 μs and a fall time of 1 ms; the current is 6 MA.

10. The compact toroid based ignition system of claim 1, wherein: The magnetic mirror holding coil set (6) has an inner diameter of 70 cm, an outer diameter of 142 cm, and a height of 50 cm, and is composed of five parallel sub-coils, each of which is a multi-turn coil with 360 turns; the coil is powered by a high-voltage power supply, with a current rise time of 1 ms and a current flat-top maintenance time of >10 ms; the magnetic mirror holding coil set (6) has a current of 10 kA per turn; the magnetic mirror holding coil set (6) is connected in time sequence with the near-center pulse coil (4) to compensate for the magnetic field drop caused by the current drop of the four near-center pulse coils (4), so that the magnetic mirror structure maintenance time is more than 10 ms to confine the fusion plasma.

11. A compact toroid based fusion ignition system according to claim 1, wherein: The neutron shielding area ratio of the tritium breeding blanket (8) is ≥99.9%, and the blanket thickness is 50-80 cm, which is relatively easy to achieve tritium self-sustaining.

12. A fusion ignition system based on compact toroid magnetic field line- thomping pulse compression technology according to claim 1, characterized in that: The coaxial gun (1) can integrate an electron cyclotron heating or neutral beam injection device to preheat and raise the outlet temperature, and the compact toroid initial velocity range is 40-400 km / s.

13. A fusion ignition system based on compact toroid magnetic field line- tripling pulse compression technique as claimed in claim 1, wherein: The system can also operate in a magnetized target fusion mode, in which compact toroids are fired from both sides again before the compact toroids formed by the collision and fusion disappear, and through cascade compression, the compact toroids collide with the magnetized target in the center, axially compress the magnetized target, and form new compact toroids through magnetic reconnection fusion to achieve higher fusion triple product parameters.

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