CN120432201A - A fusion ignition system based on compact ring magnetic cone pulse compression technology - Google Patents
A fusion ignition system based on compact ring magnetic cone pulse compression technologyInfo
- Publication number
- CN120432201A CN120432201A CN202510622954.4A CN202510622954A CN120432201A CN 120432201 A CN120432201 A CN 120432201A CN 202510622954 A CN202510622954 A CN 202510622954A CN 120432201 A CN120432201 A CN 120432201A
- Authority
- CN
- China
- Prior art keywords
- magnetic
- fusion
- compact
- pulse
- coil
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/10—Nuclear fusion reactors
Landscapes
- Plasma Technology (AREA)
- Particle Accelerators (AREA)
Abstract
The invention discloses a fusion ignition system based on a compact ring magnetic cone pulse compression technology, and belongs to the technical field of nuclear fusion energy. The system generates high-speed high-density compact ring plasma to be injected into a vacuum chamber through a symmetrical coaxial gun, a single-turn ring array triggers cascade theta pinch, the angular current of the compact ring and a self magnetic field are enhanced, a moving magnetic mirror structure is formed by combining a superconducting steady magnetic cone, and inclination instability is restrained and pushed to a central collision area. After collision fusion of the compact rings at two sides, the central magnetic mirror keeps the coil group to provide slow theta pinch so as to maintain fusion conditions, so that plasma density >10 23/m3, ion temperature >15 keV and energy constraint time >2 ms are realized, and Lawson criteria are met. The system can be switched to a magnetized target fusion mode, and axial compression and magnetic reconnection fusion are carried out by impacting the magnetized target through a secondary compact ring. The power generation module adopts cladding and electromagnetic induction dual-mode energy recovery. The technology has the advantages of compact structure, low cost, convenient maintenance and the like, and provides a new way for commercial fusion power generation.
Description
Technical Field
The invention belongs to the technical field of nuclear fusion energy, and particularly relates to a fusion ignition system based on a compact ring magnetic cone pulse compression technology, which is suitable for the development of controllable nuclear fusion energy.
Background
The ignition of the deuterium-tritium fusion needs to meet the Lawson criterion of high density, high ion temperature and long energy constraint time, namely the ignition of the deuterium-tritium fusion needs to be the fusion triple productWhile existing experimental devices are fashionable to meet the above conditions at the same time. In the past, the controllable nuclear fusion research mainly comprises two approaches of magnetic confinement and inertial confinement, wherein the magnetic confinement fusion has higher energy confinement time, for example, the energy confinement time of the current Tokamak device can reach the order of seconds, but the plasma density is usually lower and is lower than the particle density in the air by 5 orders of magnitude, while the inertial confinement fusion can obtain high plasma density which is higher than the particle density in the air by 6 orders of magnitude through compressing the target pill, but the energy confinement time is very short and is usually in the order of nanoseconds. At present, two modes are far away from commercial use of fusion energy.
The magnetic plasma collision is a technology for rapidly heating plasma, and magnetic energy can be effectively converted into plasma heat energy through magnetic reconnection, and even constraint performance is improved. The american TAE company adopts a field reversed configuration, combines two Field Reversed (FRC) plasmas into one field reversed plasma by striking them against each other, and then applies a neutral beam to increase plasma temperature and confinement performance for a duration of up to several milliseconds. Us Helion Energy has achieved plasma temperatures of 9keV, i.e. 1.1 hundred million degrees celsius, by cascading compression of field-reaction plasma, recently announced a purchase protocol with microsoft, and by 2028, the first commercial nuclear fusion generator in the world was connected to the grid and delivered to microsoft corporation.
Magnetization Target Fusion (MTF) is a fusion energy concept that combines the features of Magnetically Confined Fusion (MCF) and Inertial Confinement Fusion (ICF). Similar to the magnetic confinement method, fusion fuel, when heated to a plasma, confines a lower density plasma with a magnetic field. Meanwhile, by means of the inertial confinement method, the density and the temperature of the plasma can be remarkably improved by rapidly extruding the target substance, so that fusion reaction is triggered. The magnetic target technology combines magnetic confinement to slow down plasma loss and inertial compression heating, combines advantages of magnetic confinement fusion and inertial fusion, and opens up a new path for fusion energy development. The domestic star-energy sunlight adopts field reversed configuration and inertial compression, firstly generates FRC magnetized target plasma, then uses four cascade theta-pinch field reversed plasmas to strike and compress the FRC magnetized target, directly converts kinetic energy and partial magnetic energy of the plasma into heat energy, and has compact structure and controllable cost. MagLIF technology was proposed by the national laboratory in Mordi. Which first presets an axial magnetic field to magnetize the fuel to suppress electron heat transfer losses. And then heating the deuterium-tritium fuel to 100 eV by laser. Finally, the fuel is driven to implode by using high-power pulse current, and the fuel is compressed to a high-temperature high-density state (commonly called Z pinching), so that the fusion energy gain Q is close to 1. The General Fusion company in Canada injects deuterium-tritium glob-Mark plasma into a liquid metal inner lining, then uses a high-power piston to squeeze inwards, thereby increasing the transient pressure and density of the plasma, reducing the dependence on extremely high temperature and reaching the condition of Fusion reaction, and simultaneously, the Fusion reaction can generate neutrons which can react with lithium in the liquid metal to generate more tritium. Fusion conditions of more than one hundred million degrees celsius were planned to be achieved before 2025, and a profit and loss balance point was planned to be reached in 2026, and commercial fusion energy was provided to the grid in the mid-first-to-mid 2030. Therefore, the magnetized target fusion combines the advantages of prolonging the energy constraint time in magnetic constraint and high density in inertial constraint, becomes an emerging fusion path, and shows strong market competitiveness.
In the case of magnetized plasmas, the energy confinement time is typically between Bohm @) And the whirling Bomu) And plasma specific pressure representing the ratio between magnetic pressure and hot pressureThe fusion triple product can therefore be written asThis represents the need for a strong magnetic field and a high specific pressure to achieve fusion ignition.
In recent years, the high-temperature superconducting technology is mature gradually, and a new opportunity is brought for magnetic confinement fusion. Because the specific pressure of the tokamak and the star simulator is low (1-5%), the volume is large, and the superconducting materials are needed, so that the device cost is high. Meanwhile, the three-dimensional coil of the star simulator and the D-shaped coil of the tokamak are limited by material stress, and the magnetic field intensity at fusion reaction is limited. In order to exert the advantage of the high-temperature superconducting strong magnetic field to the maximum extent, it is desirable to make fusion occur at the center of the circular-section solenoid and reduce the radius of the high-temperature superconducting coil.
In the technical field of strong magnetic field generation, the current main flow scheme mainly depends on two main technical routes, namely a steady-state strong magnetic field system based on a high-temperature superconducting material and a pulse strong magnetic field system based on a low-inductance copper coil framework. The high-temperature superconducting coil can maintain a steady-state magnetic field of tens of Tesla magnitude under a 4.2K low-temperature environment by virtue of the characteristics of high critical current density and negligible joule heat loss, and a pulse strong magnetic field system can realize transient magnetic field strength exceeding 100T by using an optimized coil inductance design and a high-power pulse power supply (peak current reaches MA magnitude and pulse width mu s-ms magnitude). By constructing the composite magnetic field generating system, the total field intensity is obviously improved. The bimodal magnetic field synergistic mechanism breaks through the physical limit of the traditional single field source, realizes the advantage complementation of the stability of a steady magnetic field and the strength of a transient magnetic field, and opens up a technical path with engineering expandability for fusion reactor engineering design.
For the topology of the magnetized plasma, all open magnetic line schemes have too short energy confinement time due to terminal loss to reach the lawson criterion. At present, 3 closed magnetic configurations are most promising for realizing the fusion energy sources, namely Tokamak (comprising a spherical ring and having the highest technical maturity), a star simulator (having steady-state advantages but being most difficult to manufacture) and a compact ring (having the simplest structure and lowest cost). Coaxial guns are flexible tools in nuclear fusion research that use electromagnetic forces to create high-speed, high-density compact loops. The compact ring generated by the coaxial gun is similar to the spheromak plasma, has a circumferential magnetic field and a polar magnetic field, is more stable relative to the field inverse plasma, and more importantly, can realize high specific pressure of the plasma。
The invention uses the coaxial gun to generate the compact ring, the pulse coil group is cascaded with theta pinch, the high-temperature superconducting strong field is compressed in a heat-insulating way, the magnetic mirror inhibits the instability of the compact ring, and the compact ring is compressed to the center of the magnetic cone for collision fusion, so as to achieve fusion ignition conditions. The scheme introduces a high-temperature superconductive strong magnetic field into a field demagnetizing compression technology, combines a coaxial gun compact ring, and exerts the strong magnetic field and high specific pressure to the extreme of the current technical level.
Disclosure of Invention
The invention provides a stacking transformation ignition system based on a compact ring magnetic cone pulse compression technology, which is characterized in that two high-speed high-density compact rings are generated through a coaxial gun, a pulse coil which is axially distributed is used for completing cascade theta pinch of the compact rings, a movable magnetic mirror formed by the pulse coil and a superconducting hybrid magnet is used for restraining the compact rings, the inclination instability of the compact rings is restrained, the compact rings are pushed into the center of a magnetic cone formed by the superconducting hybrid magnet, collision fusion is completed, a magnetic mirror is further maintained and reinforced through a magnetic mirror holding coil group, deuterium-tritium fusion ignition and direct power generation are realized, and the defects of high cost and low efficiency of the traditional technology are overcome.
The system can also operate in a magnetized target fusion mode, and before the compact loops formed by collision fusion disappear, the compact loops are launched again from two sides, the central compact loop magnetized target is impacted by cascade compression, the central compact loop magnetized target is axially compressed, and a new compact loop is formed by magnetic reconnection fusion, so that higher fusion three-times product parameters are achieved.
English name of the system:
MAGIC (Magnetic-cone Adiabatic Gradient-force Impulsive Compressor) Magnetic cone adiabatic gradient force pulse compressor.
The technical scheme of the invention is as follows:
A fusion ignition system based on compact ring magnetic cone pulse compression technology comprises
Symmetrically distributed coaxial guns for producing high speed, high density compact rings;
The axial center of the vacuum chamber is a plasma collision zone, the vacuum chamber wall of the collision zone is made of non-magnetic stainless steel, the other parts are quartz, tungsten tiles are placed at the two ends of the vacuum chamber and the inner wall of the collision zone, and a tungsten copper water cooling structure is adopted;
The conventional pulse coils are axially and symmetrically arranged along the vacuum chamber and are composed of single-turn niobium-copper coils and N50 nonmagnetic stainless steel, and are sequentially triggered to generate a transient magnetic field to push the compact ring, and the pulse coils close to the center participate in the maintenance of fusion reaction;
a magnetic mirror holding coil group arranged below the superconducting hybrid magnet, generating a confinement field for tens of milliseconds to maintain fusion reaction;
The superconducting hybrid magnet is arranged in the collision area and is formed by mixing a high-temperature superconducting magnet and a low-temperature superconducting magnet, and a steady-state magnetic cone constraint field is generated;
tritium proliferation cladding surrounds the vacuum chamber and the coaxial gun port, all the cladding angles are insulated and cut off, so that the magnetic field permeation is facilitated, and a staggered structure is adopted to avoid neutron leakage;
The low-temperature superconducting reverse magnets are symmetrically arranged at the periphery of the joint of the coaxial gun outlet and the vacuum chamber and used for adjusting the magnetic field intensity at the coaxial gun outlet;
and the power generation module realizes dual-mode power generation through neutron moderation of thermal energy power generation and electromagnetic induction magnetic energy recovery.
In the technical scheme, the coaxial guns are symmetrically distributed at two ends of the vacuum chamber and are used for generating high-speed and high-density compact rings, working gas is mixed fuel of deuterium and tritium, plasma is formed by high-pressure pulse ionized gas, and the plasma is accelerated by Lorentz force;
In the technical scheme, the vacuum chamber is a long cylinder with a flat lying circular section, the axial center of the vacuum chamber is a plasma collision area, the vacuum chamber at the collision position is made of non-magnetic stainless steel, an insulating partition is arranged in the angle direction, the inner wall of the vacuum chamber covers a tungsten tile, and a channel of compact rings at two sides of the vacuum chamber along the axial direction of magnetic force lines is formed by a quartz tube or a silicon carbide fiber reinforced ceramic matrix composite material. Tungsten tiles are placed at the two ends of the vacuum chamber and the inner wall of the collision area, so that high-energy particles are prevented from damaging the wall of the vacuum chamber along magnetic lines. A boronated wall treatment may be employed to reduce metal impurities in the plasma;
In the technical scheme, the pulse coils are axially and symmetrically arranged along the vacuum chamber, the pulse coils are sequentially triggered to generate a transient magnetic field, the transient magnetic field and a strong magnetic field generated by the superconducting hybrid magnet form a movable magnetic mirror structure together, a constraint compact ring is captured, the compact ring is rapidly and stably pushed to reach the central area of the magnetic cone, the pulse coils are jointly formed by a plurality of single-turn coils, the pulse coils are made of niobium copper or copper-chromium alloy, and N50 nonmagnetic stainless steel is welded on the outer side of the pulse coils to strengthen the mechanical strength;
In the technical scheme, the superconducting hybrid magnet is arranged in the collision area of the central tube, a steady-state strong magnetic field is generated at the axial central position of the vacuum chamber by the superconducting hybrid magnet, a magnetic cone constraint field is formed by extending magnetic lines to two sides of the collision area, the magnetic cone gradually compresses the compact ring in the process of moving the compact ring to the collision area, the density and the temperature of the compact ring are increased, the compact rings at the left end and the right end are coaxially collided with each other, a pulse coil group close to the center is formed, the adjacent magnetic mirror keeps the coil group and the superconducting hybrid magnet to jointly form a reinforced magnetic mirror so as to restrain fusion reaction of tens of milliseconds, and the superconducting hybrid magnet is formed by parallelly mixing high-temperature superconduction and low-temperature superconduction from inside to outside;
In the technical scheme, the magnetic mirror holding coil group is arranged below the superconducting hybrid magnet and surrounds the tritium proliferation cladding in the central area, the magnetic mirror holding coil group consists of a plurality of wider coils, and the magnetic mirror holding coil group is externally connected with N50 nonmagnetic stainless steel;
In the technical scheme, the tritium proliferation cladding surrounds the whole vacuum chamber and part of ports of the coaxial gun, the tritium proliferation cladding is also arranged between the vacuum chamber and the superconducting hybrid magnet and used for neutron moderation and radiation shielding, all tritium proliferation cladding angles are isolated and insulated, so that permeation of a magnetic field is facilitated, and meanwhile, the tritium proliferation cladding adopts a staggered structure to avoid neutron leakage;
in the technical scheme, the low-temperature superconducting reverse magnets are arranged on two sides of the superconducting hybrid magnet and are positioned 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 at the outlet of the coaxial gun;
In the technical scheme, the power generation module not only can absorb neutrons slowly in the tritium proliferation cladding layer and convert the neutrons into heat energy to generate power, but also can directly generate power through electromagnetic induction. After fusion reaction, the hot pressing of the plasma is increased, the volume is expanded, and the confinement of the magnetic mirror is preferentially escaped from the axial direction with weaker magnetic confinement. The magnetic fluid passes through the coil array channel, changes coil current through electromagnetic induction, is directly converted into electric energy, and realizes energy recovery through the insulated gate bipolar transistor. Meanwhile, after alpha particles generated by fusion escape through a loss cone of the magnetic mirror, the particles axially move along magnetic force lines to form current, and energy is fed back to the capacitor through a single-turn ring by electromagnetic induction, so that the energy is recovered.
The beneficial effects are that:
The invention provides a fusion ignition system based on a compact ring magnetic cone pulse compression technology, which is characterized in that a high-speed and high-density compact ring is injected into a vacuum chamber through a coaxial gun technology. And then, mutually coupling a cascade pulse magnetic field excited by the pulse coil group and a stable magnetic cone generated by the superconducting hybrid magnet to jointly construct the dynamic magnetic mirror structure. The compact ring is effectively captured and restrained by the magnetic mirror, and is subjected to a cascade theta pinch compression heating process, and meanwhile, the compact ring moves towards a central collision area under the driving of the magnetic mirror force, and finally collides and merges with the compact ring which is also subjected to the process at the other end. Pulse coil groups and magnetic mirror holding coil groups which are close to the center on two sides of the center axis of the magnetic cone generate a reinforced magnetic mirror structure of tens of milliseconds together with the superconducting hybrid magnet, and the high-temperature and high-density compact ring is restrained to realize the fusion ignition of deuterium and tritium. In the pulse coil and the superconducting magnetic cone field, the plasma follows the principle of conservation of magnetic flux, the volume of the compact ring and the magnetic field are in inverse proportion relation, the density and the magnetic field show positive correlation relation, and the plasma density can be improved to Ion temperature reachesEnergy constraint timeSatisfies fusion triple product required by deuterium-tritium fusion ignition. The compact toroid itself superimposed with 30T of background magnetic field will produce a magnetic field in excess of 50T with a magnetic pressure sufficient to balance the hot pressing of fusion plasma. Some plasma turbulence and instability do not readily occur under such strong magnetic fields, e.g., due to Alfven speedsThe Alfven eigenmodes excited by some high-energy particles are not easily excited because they are high under strong magnetic fields.
In addition, as the magnetic cone compresses and guides the compact ring to the central position of the vacuum chamber, the fusion position is far away from the wall of the vacuum chamber, and the interaction between the plasma and the wall and the damage of high-energy particles to the wall are weakened. Meanwhile, the magnetic energy stored in the coil inductance can be recovered through a circuit due to the short energizing time of the pulse coil, so that the energy consumption of the coil system is low. The service life of the components such as the niobium-copper coil, the insulation and the vacuum chamber under neutron irradiation is more than 3 years, and the components are used as consumable materials and have low replacement cost. Moreover, the elimination of the auxiliary heating system is a significant advantage, as the auxiliary heating systems of tokamaks and star simulators are not only costly but also generally have poor operational reliability. The device has the advantages of modular design of all main parts, simple and compact structure, and convenience for daily maintenance, disassembly, assembly and replacement. The volume and the cost of the whole fusion reactor are only 1/100 of that of the tokamak and star simulator fusion reactor, so that the economic competitiveness of fusion energy is obviously improved, the electricity cost is reduced, and the fusion reactor has great potential value. Therefore, the invention is novel, inventive and practical.
Drawings
FIG. 1 is a transverse vertical sectional view of a compact toroid magnetic cone pulse compressor;
FIG. 2 is a current waveform of a microsecond pulse coil, a near center pulse coil, and a magnetic mirror holding coil set;
FIG. 3 is a schematic view of a1×10 structure of a single turn ring and a 3×10 terminal block;
FIG. 4 is a spatial distribution diagram of the magnetic field generated by the magnetic mirror holding coil assembly in the axial direction;
FIG. 5 is a spatial distribution diagram of the steady-state magnetic field generated by a superconducting hybrid magnet in the axial direction;
FIG. 6 is an axial distribution diagram of a mixed magnetic field in a vacuum chamber at different times;
FIG. 7 is a schematic diagram of a magnetic mirror capturing compact toroid magnetic field configuration;
FIG. 8 is a graph of parameterized simulation results of COMSOL particle tracking;
FIG. 9 is a graph of simulation results of fusion combustion share over time under different constraint time constants.
In the figure:
The coaxial gun comprises a coaxial gun body, a vacuum chamber, a conventional pulse coil assembly, a pulse coil assembly close to the center, a superconducting hybrid magnet, a magnetic mirror holding coil assembly, a low-temperature superconducting reverse magnet, a tritium-added cladding layer, a gas injection port, a single-turn coil, non-magnetic stainless steel (11N 50) and a power generation module.
Detailed Description
The technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present invention, and it is apparent that the described embodiments are only some embodiments of the present invention, but not all embodiments, and all other embodiments obtained by those skilled in the art without the inventive effort based on the embodiments of the present invention are within the scope of protection of the present invention.
Examples
As shown in fig. 1, this embodiment proposes a fusion ignition system based on a compact ring magnetic cone pulse compression technique. The high-speed compact ring is generated through the coaxial gun, the pulse coil assembly utilizes the cascade theta pinch effect and is coupled with the magnetic cone of the superconducting hybrid magnet, constraint, compression and collision of the compact ring are cooperatively completed, deuterium-tritium fusion ignition is realized, and the dual-mode power generation is realized through neutron moderated heat energy power generation and electromagnetic induction magnetic energy recovery. The system comprises a coaxial gun 1, pulse coil groups (3 and 4), a magnetic mirror holding coil group 6, a superconducting hybrid magnet 5, a low-temperature superconducting reverse magnet 7, a vacuum chamber 2, a tritium value-added cladding 8 and a water cooling system.
The coaxial guns 1 are symmetrically distributed at two ends of the vacuum chamber 2, plasma is formed by high-pressure pulse ionization gas, and high-speed (40-400 km/s) and high-density (approximately 1 multiplied by 10) are generated by Lorentz force 22 ) The repetition pulse frequency can reach 50Hz at most, the upper end of the coaxial gun 1 is provided with a fuel gas injection port 9, the fuel gas is mixed fuel with 50 percent of deuterium and tritium respectively, and the caliber of the coaxial gun 1 can be set to be 10-30cm according to actual requirements;
The vacuum chamber 2 is arranged in the center of the whole device, the whole axial length of the vacuum chamber is 8m, the outer diameter of the vacuum chamber is 38 cm, and the wall thickness of the vacuum chamber is 2 cm. The wall of the whole vacuum chamber 2 except the collision area is made of quartz material, the axial center of the vacuum chamber 2 is a plasma collision area, the wall of the vacuum chamber at the collision position is made of non-magnetic stainless steel, the inner wall is covered by tungsten tiles, a tungsten copper water cooling structure is adopted, and the angle direction is insulated and isolated, so that electromagnetic shielding is avoided. The strong magnetic field of 20T limits the expansion of the plasma across the magnetic field lines to weaken the plasma interaction with the wall. An important benefit of using magnetic cone compression rather than conical conductor wall compression is that the compressed plasmoid is kept away from the walls, and in particular the volume of the plasmoid expands after fusion, which reduces the interaction between the plasmoid and the walls, reduces impurity radiation, and prolongs the life of the internal components in the vacuum chamber.
The inner walls of the two end surfaces of the cylindrical vacuum chamber at the outlet position of the coaxial gun 1 at the two sides of the vacuum chamber 2 are tungsten tiles, and a tungsten copper water cooling structure is adopted to bear interaction of particles escaping along magnetic force lines. A circle of gaps are formed at the edges of two end surfaces of the cylindrical vacuum chamber and are used as extraction openings, a filter structure similar to Tokamak is adopted, and an extraction system such as a cryopump or an adsorption pump is externally connected to discharge fusion products and unreacted fusion fuel gas to form fuel circulation;
The number of the conventional pulse coil groups 3 is 26, and the conventional pulse coil groups are symmetrically arranged along the axial direction of the vacuum chamber 2. The material of the conventional pulse coil assembly 3 can be changed according to practical requirements, for example, a niobium-copper alloy with high yield strength suitable for high mechanical stress environment can be selected, and a copper-chromium alloy with excellent irradiation resistance can be selected. The single-turn ring pulse coil is preferably made of niobium-copper alloy, mainly considering that the single-turn ring pulse coil has higher yield strength (up to more than 800 MPa), has stronger fatigue resistance and longer service life under the repeated pulse operation condition, and has lower resistivity when the content of niobium is below 1 percent. However, niobium copper alloys have inferior neutron irradiation resistance to copper chromium alloys, which have lower yield strengths (about 500-700 MPa). If the conventional pulse coil group 3 is made of copper-chromium alloy, fatigue cracks are estimated to appear after about 10 4-105 pulses, and the cycle life of the coil can be prolonged by developing niobium-copper nanocrystalline alloy later. The N50 nonmagnetic stainless steel 11 is welded on the outer side of each pulse coil to strengthen the mechanical strength. The temperature rise of the coil is negligible because the time the current passes through the coil is too short.
The conventional pulse coil assembly 3 and the pulse coil assembly 4 close to the center are sequentially triggered to generate a transient magnetic field, and the mutual coupling of the transient magnetic field and the strong magnetic field generated by the superconducting hybrid magnet 5 can be regarded as a magnetic mirror structure moving axially. The current rise time constant in the conventional pulse coil group 3 is about 2 microseconds, the down time constant is about 50 microseconds, and the coil current of the conventional pulse coil group 3 gradually becomes from the two ends to the middleThe current rise time in the pulse coil set 4 near the center is about 2 microseconds, the down time constant is about 1 millisecond, and the current of all coils is。
The transient change time of the magnetic field in the strong magnetic field is far longer than the cyclotron period of the particles, the magnetic moment conservation condition is met, and the square direct ratio of the vertical velocity and the magnetic field are obtainedThe rapid change of the magnetic field generated by the single-turn pulse coil assembly 3 realizes energy transfer through the unbalanced interaction of the electromagnetic field and the particles, the change of the magnetic field generates an induced electric field, the particles are compressed by rapid adiabatic magnetism, the vertical speed of the particles is increased, and the magnetic energy is changed into the energy of the particles. The rapid adiabatic magnetic compression has square relation to the vertical pressure rise and the magnetic field strength, namely the vertical hot pressing and the magnetic pressure are synchronously raised, and meanwhile, the compact ring before the magnetic cone compression is a compact ring with high beta, the compression can be obtainedIs a plasma of (a). In the initial compact form, the initial directional kinetic energy of the particles is less than 1keV to raise the temperature even if it is completely converted into thermal energy, so the directional kinetic energy is not a main energy supply source.
The most critical of the linear device is to restrain the loss in the axial direction, and the combination of the self-restraint of the compact ring and the dynamic magnetic mirror in the invention realizes the double restraint on the axial transportation. On the one hand, the closed magnetic field topological structure of the compact ring can effectively reduce the terminal loss of particles in the axial direction. On the other hand, the dynamic magnetic mirror is adopted in the axial direction to restrain the compact ring, and the axial loss of particles is further reduced by the magnetic mirror. At the same time, the plasma temperature at the compression start point is very low and the axial velocity is very low due to the coaxial gun outlet. During the movement of the compact toroid, the axial direction has no effective acceleration mechanism for the compact toroid, while the collision energy exchange time in the parallel and perpendicular directions is much longer than the compression time, the axial direction will remain at low temperature and low speed all the time, so a shallower magnetic mirror can constrain the compact toroid well. Because the heat conductivity of electrons in the direction parallel to magnetic force lines is far greater than that of ions, and the collision energy exchange time of electrons and ions is far longer than that of compression time, higher ion temperature can be obtained, the ion temperature in the magnetic mirror is kept far higher than that of electrons, and the energy loss of bremsstrahlung and gyrotron can be reduced by lower electron temperature. If it isThe state of (c) can be stably maintained as long as the required fusion triple product can be achieved, deuterium-deuterium fusion (helium-3-containing) and proton-boron fusion are also possible in principle, which means inexhaustible fusion fuel and avoids the problem of radioactive safety of tritium.
The pulse coil group 3 and the pulse coil group 4 near the center are the single-turn coil 10 of niobium-copper alloy containing 1% niobium, the inner diameter is 40cm, the axial height is 15cm, and the radial thickness is 7cm. Considering the current skin effect of microsecond pulse current on a single-turn loop, silver plating can be considered on the surface of the single-turn loop to reduce the surface resistance of the single-turn loop. Multiple insulated fine wires may be used in parallel (litz wire configuration) to disperse the high frequency current paths. The total surface area of the stranded wires is larger, so that the skin effect can be weakened, and the overall inductance is reduced through parallel connection. The coaxial cable with the length of 20 meters is connected with a capacitor to supply power for the coil, the outer diameter of the cable is 4cm, and the total resistance is calculatedTotal inductance of cable. The resistance and inductance of the single turn loop is much less than the resistance and inductance on the loop, so the resistance and inductance of the single turn loop is negligible. The conventional 26 coils are powered by a low-inductance fast discharge vessel, the voltage across the capacitor is about 100kV,Through series connection of resistors R-0.5Current rise time constant of RLC loopFalling time constantAs shown in fig. 2 (a). The four pulse coils 4 close to the center have high current, the total current is 6MA, and the maintenance time is in the order of milliseconds, so that 30 power supplies are used for supplying power to a single-turn ring in parallel. Each 200kA, the joints were designed in a 3 x 10 array as shown in fig. 3 (a) and (b). The power supply may be performed using an ultra-high voltage power capacitor,Current rise time of RLC loopFalling time constantThe discharge waveform is shown in fig. 2 (b). The repetition frequency of the overall system depends on the capacitor charging time. Theoretically the highest repetition frequency can reach 50Hz.
In the compact toroid, the lorentz force of the angular current and the background magnetic field is the core confinement force that maintains the plasma balance. The electromagnetic force effectively resists two main expansion effects, namely radial expansion force driven by hot-pressing strong gradient and magnetic tension generated by interaction of polar current and self-generated angular magnetic field through a MHD balance mechanism. The pulse coil system has a dual mechanism in the constraint of electromagnetic fields, namely, on one hand, the transient magnetic field energy of a coil and two magnetic fields generated by a superconducting hybrid magnet are coupled to form a constraint bit type of a dynamic magnetic mirror, so that a compact ring can be captured and the inclination instability of the compact ring can be restrained by means of magnetic mirror force, and therefore the compact ring is stably pushed from a low magnetic field region to a high magnetic field region of a magnetic cone, and on the other hand, when the compact ring sequentially passes through the pulse coil array, the angular current in the compact ring is continuously enhanced and the compact ring structure is continuously compressed and stabilized by generating a cascading theta pinch effect. Meanwhile, the pulse time of the pulse coil array is short, so that the rotation instability can be avoided, and the generation of cracking is avoided.
The two magnetic mirror holding coil groups 6 are arranged at the periphery of the pulse coil group 4 near the center for compensating for the magnetic field drop during the current drop of the four pulse coils 4 near the center. Each magnetic mirror holding coil group 6 is composed of five parallel sub-coils, the inner diameter is 70cm, the outer diameter is 142cm, the height is 50cm, each sub-coil is a multi-turn coil with 360 turns, and the coil current is equal to the coil currentRespectively using 5 power supplies to synchronously supply power and inductanceResistance, resistanceThe loop resistance was configured to 17.6 by resistor seriesCoil drive voltage. Discharge current waveform. Current rise timeAnd maintained a plateau for more than 10 milliseconds. The magnetic field distribution of the coil current of the magnetic mirror holding coil group reaches the peak value as shown in fig. 4, and the magnetic mirror is coupled with the background magnetic field shown in fig. 5 to form a quasi-steady state magnetic mirror capable of restraining a compact ring. The capacitor energy storage for supplying power to the pulse coil can be changed into superconducting inductance energy storage, so that the volume of a power supply is greatly reduced, and the power supply can be applied to occasions needing miniaturization such as spacecrafts and aircraft carriers in the future.
The superconducting hybrid magnet 5 is arranged in the central collision area, and the superconducting hybrid magnet 5 is arranged in parallel from inside to outside by high-temperature superconductivity and low-temperature superconductivity. The superconducting hybrid magnet 5 can generate a steady-state strong magnetic field at the axial center position of the vacuum chamber 2, the magnetic line extends to two sides of the collision area to form a magnetic cone structure, and the maximum magnetic field strength at the peak top of the magnetic cone can reach 20T, as shown in fig. 5. The compact ring is gradually compressed in the process of being pushed to the center to move under the action of the transient magnetic field generated by the pulse coil 3, and when the magnetic compression time is shorter than the magnetic diffusion timeMagnetic freezing conditions are satisfied, and magnetic flux conservation. Assuming the length of the compact toroid along the direction of the magnetic linesThe volume is reduced with the increase of the magnetic fieldBased on conservation of particle numberConstant, the density increases with the increase of the magnetic fieldAt the peak of the magnetic cone, the inner diameter of the compact toroid is compressed to 1/20 of that of the coaxial gun outlet, so that the compact toroid is far away from the vacuum chamber wall, reducing the interaction of plasma and wall, and raising the compact toroid density to. According to conservation of magnetic moment, vertical temperature increases with increasing magnetic fieldThe vertical pressure increases with the square of the field enhancement. In the process, external magnetic pressure applies work, and electromagnetic field energy is transferred to plasma, so that compression and heating are realized. After the compact rings at the left end and the right end are coaxially collided, the magnetic field undergoes a magnetic reconnection process, and a large amount of magnetic energy is released to be converted into heat energy. This process not only enhances the confinement capacity of the total magnetic field, but also further heats the plasma. The magnetic field at the collision fusion is in fact the superposition of the steady-state magnetic field of the superconducting hybrid magnet 5, the magnetic field generated by the 4 pulse coils 4 closest to the center, the magnetic mirror holding coil set 6 and the residual magnetic field after the compact ring magnetic reconnection. The mixed magnetic field jointly constrains the fusion reaction for more than 5 times the energy constraint time. The range of parameters for the compact toroid at the exit of the coaxial gun, the range of parameters for the compact toroid at the center impact zone, and the fold change in parameters are shown in the table below.
TABLE 1 compact disc parameter Range and parameter fold Change
The system can also operate in a magnetized target fusion mode, and before the attenuation of the high beta compact loops formed by initial collision fusion disappears, secondary compact loops are synchronously injected from two sides again, the central compact loop magnetized target is impacted by cascade compression, axial compression is carried out on the central compact loop magnetized target, and a new compact loop is formed by magnetic reconnection fusion, so that higher fusion three-product parameters are achieved.
The heating scheme of the pulse coil array and the high-temperature superconducting magnetic cone has a plurality of unique innovation points. The compact toroid generated by the coaxial gun has a significantly enhanced angular magnetic field component compared to the plasmoid generated by the FRC, which exhibits comparable strength characteristics as the polar magnetic field. This unique magnetic topology is advantageous for pulse coils to induce stronger angular induced currents in the compact toroidal plasma through the flux compression effect. The compact ring can be regarded as a moving secondary winding of the dynamic magnetic coupling transformer, and forms an electromagnetic induction coupling system with time-space accurate modulation with a primary winding formed by the pulse coil array, wherein when the compact ring axially passes through the pulse coil array, each primary unit is excited by transient magnetic flux controlled by time sequence, and a cascading theta pinch effect is generated. The theta pinch of the compact ring is similar to the Tokamak polar field system, polar magnetic flux penetration is generated by fast rising current, electron current along spiral magnetic force lines is induced in a plasma ring, a self-contraction potential well which is inward in radial direction is formed by E X B drift, and the centering motion of electrons in a strong spiral magnetic field generates nonlinear coupling of a forward magnetic polar current component and a reverse magnetic angular (annular) current component, so that a stronger angular (annular) magnetic field and a reverse axial magnetic field are generated. When the compact ring continuously passes through the multi-stage coil, the cascade theta pinch effect gradually amplifies the angular (circumferential) current density, and the generated self-consistent magnetic field and the magnetic shear layer formed by the background magnetic field can effectively inhibit instability of the inclined mode and the tearing mode, so that dynamic stability is realized. The cascading theta pinch process can be analogically modeled as a gyroscopic acceleration model in which an array of distributed pulsed coil arrays (analogically whip-holder arrays) are controlled in precise coordination as the compact toroid (analogically rotating gyroscopes) advances in the direction of the magnetic axis, applying directional energy injection as the compact toroid traverses each coil, increasing gyroscopic energy. Compared with a central solenoid heating scheme of Tokamak, the energy deposition strategy breaks through the limitation of the number of volts per second of a single coil, and can realize rapid compression heating of plasma by enhancing a magnetic field and current, so that the density and the temperature of the plasma are greatly increased within a sub-millisecond time, and finally, an extreme parameter running state is achieved.
The tritium proliferation cladding 8 covers the whole vacuum chamber 2 and part of the muzzle of the coaxial gun 1, the coverage area of the cladding 8 can reach more than 99.9%, tritium self-holding is easy to realize, and meanwhile, the vacuum chamber 2 and the superconducting hybrid magnet 5 are separated by the tritium proliferation cladding 8, and the main functions of the tritium proliferation cladding are neutron moderation and radiation shielding. All tritium breeder cladding 8 is provided with isolating and insulating means in the angular direction to promote magnetic field penetration. In addition, the tritium proliferation cladding 8 adopts a staggered structure design, so that neutron leakage is effectively prevented;
The low-temperature superconducting reverse magnets 7 are arranged on two sides of the superconducting hybrid magnet 5 and are positioned at the joint of the port of the coaxial gun 1 and the vacuum chamber 2, and can generate a magnetic field opposite to the superconducting hybrid magnet 5 to offset a static magnetic field generated by the superconducting hybrid magnet 5 so as to increase the magnetic field intensity drop from the edge to the center, thereby realizing the function of controlling the magnetic field intensity at the outlet of the coaxial gun 1 and avoiding the magnetic field from influencing the normal operation of the coaxial gun;
The power generation module 12 can only utilize neutrons generated by fusion to be slowly absorbed in a tritium proliferation cladding, convert the neutrons into heat energy for power generation, and can also directly generate power through electromagnetic induction. After fusion reaction, the hot pressing of the plasma is increased, the volume is expanded, and the confinement of the magnetic mirror is preferentially escaped from the axial direction with weaker magnetic confinement. The magnetic fluid passes through the coil array channel, causes coil current change through electromagnetic induction (similar to an electromagnetic braking principle), is directly converted into electric energy, and then realizes energy recovery through a switching circuit formed by Insulated Gate Bipolar Transistors (IGBTs), the recovery efficiency of >90% can be realized theoretically, the traditional heat exchange system and steam turbine power generation are not needed, and the highest efficiency can only reach 35%. And simultaneously, after alpha particles generated by fusion escape from the compact ring and the magnetic mirror, the particles axially move along magnetic force lines. The radius of revolution of the alpha particles in a 30T magnetic field is about 9 mm, which determines the minimum inside diameter of the vacuum chamber. The impact moderation time is in the hundreds of microseconds and the swirling radiation helps to slow down the alpha particles. The alpha particles escaping through the loss cone of the magnetic mirror form current, and energy is fed back to the capacitor through a single-turn loop by electromagnetic induction. In the whole process, the single-turn loop pulse coil has short power-on time, extremely low resistance, less Joule heat generation and low energy consumption, and simultaneously, most of magnetic energy stored in the single-turn loop inductor can realize energy recovery through an RLC series circuit to reversely charge a capacitor, thereby further reducing the energy consumption of a coil system;
The simulation of the distribution of the mixed magnetic field at different moments on the axis of the vacuum chamber 2 in a single ignition experiment is shown in fig. 6, where at the initial moment of t=0 microseconds, only the steady state magnetic cone generated by the superconducting hybrid magnet 5 is present. In the next 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 restraining compact ring, as shown in fig. 7, and the sequential triggering of the pulse coils changes the magnetic mirror structure into a moving magnetic mirror, and in the process, the compact ring is gradually compressed and stably pushed into the collision area. At t= 25.9631 microseconds, the compact loops at the two ends collide and fuse, then the magnetic mirror holding coil group 6 is triggered, and the generated magnetic field gradually replaces the magnetic field of the pulse coil close to the center, so that the compact loops are ensured to burn stably in the collision area until the fusion reaction is finished.
The motion trail of single ions along with the change of magnetic field is simulated under the given coil parameters. The rising time constant of the coil pulse current and the initial speed of the compact toroid are parametrized by a particle tracking program, and the scanning result is shown in fig. 8, wherein red represents that the compact toroid can finally reach the magnetic field center, and blue represents that the compact toroid can not finally reach the magnetic field center. The simulation result shows that the coil rise time constant is smaller than 40 mu s, and the initial speed of the compact ring is larger than 130km/s and smaller than 200km/s, which is the safe operation interval of the device.
Assuming that the ratio of deuterium to tritium in the plasma is 1:1 after collision of the compact rings, the density reaches 10 23 per cubic meter, the temperature is 15 keV, and the time constant of fusion combustion reaction is about 40ms according to the deuterium to tritium reaction section. Due to losses such as plasma diffusion, deuterium and tritium cannot all undergo fusion reaction, and the final reaction share of the fusion reaction is related to parameters such as time constant of the fusion reaction, particle confinement time of a compact ring and the like. As shown in (a), (b), and (c) of fig. 9, the variation of the combustion share of the plasma with time under different particle confinement time constants of the compact toroid was simulated under this plasma parameter. Simulations show that if the particle confinement time constant is 1ms (10 ms), its final combustion fraction can reach 2.4% (20%) beyond the predicted parameters for future fusion tokamak devices.
The system is suitable for building 100 MW-level small fusion stacks, can be flexibly deployed into distributed energy units, can be directly embedded into high-energy consumption facilities such as an AI computing center, a heavy industrial base and the like to realize near zero-loss energy supply, or a GW-level large fusion power station is formed by a plurality of fusion stack units, and becomes an regional energy hub to provide continuous and stable power output. The intelligent energy system can effectively solve the problems of intermittence and fluctuation of wind and light caused by weather and day and night, forms a double-track mode of 'local green electricity + remote nuclear aggregation', and improves the economical efficiency and stability of the whole energy.
The revolutionary breakthrough is more embodied in the field of deep space power, and because the fusion reactor has small volume and high fusion three-product, a deuterium-helium 3 fusion scheme can be adopted to reduce neutron flux, and the fusion reactor can be possibly installed in an aircraft, so that interstellar travel is possible. In addition, the system can be changed into an open structure at one end, and a magnetic nozzle is adopted to spray the plasma mass outwards, so that the high-thrust long-endurance deep space propeller is directly formed.
If fusion parameters need to be improved in the follow-up process, the power of the coaxial gun is improved to MW level to improve the density, temperature and directional movement speed of the compact ring at the outlet of the coaxial gun, and the magnetic field strength is improved to increase the energy constraint time of the compact ring.
The above embodiment provides a fusion ignition system based on compact ring magnetic cone pulse compression technology, the system utilizes the coaxial gun 1 to generate high-density and high-speed initial compact rings, the initial compact rings are injected into a vacuum chamber, the conventional pulse coil set 3 and the pulse coil set 4 close to the center are sequentially electrified to generate cascade transient electromagnetic fields which are coupled together with stable background strong magnetic fields generated by the superconducting hybrid magnet 5 to form a dynamic magnetic mirror structure, the compact rings are rapidly and stably pushed to the central region of the magnetic cone, meanwhile, the compact rings are continuously compressed by utilizing the cascade theta pinch effect and the magnetic cone strong magnetic fields to enable the compact rings to obtain higher-order density and energy, and finally the compact rings generated by the coaxial gun 1 distributed at two ends are mutually collided and fused in the central collision region of the magnetic cone to generate fusion. During fusion, the magnetic mirror holding coil set 6 receives the magnetic field generated by the pulse coil to stabilize the magnetic mirror structure of the collision area until the compact ring plasma combustion is finished. The combination of the self-restraint of the compact ring and the dynamic magnetic mirror realizes the double restraint of axial transportation and can solve the problem of terminal loss of the linear device. The system can realize deuterium and tritium ignition at the present stage, and has the characteristics of simple structure, convenient maintenance, low cost and the like.
Parts of the invention not described in detail are well known in the art.
While the foregoing has described the embodiments of the present invention in further detail, it should be apparent that the present invention is not limited to the embodiments, but is intended to cover all modifications, substitutions, etc. which are obvious to those skilled in the art, as well as all modifications and the invention which make use of the inventive concept, as long as they fall within the spirit and principle of the present invention as defined and defined by the appended claims.
Claims (13)
1. A fusion ignition system based on compact ring magnetic cone pulse compression technology, comprising:
Symmetrically distributed coaxial guns (1) for producing high-speed high-density compact rings;
The axial center of the vacuum chamber (2) is a plasma collision zone, the wall of the collision zone vacuum chamber is made of non-magnetic stainless steel, the walls of the other vacuum chambers are made of quartz, tungsten tiles are placed at the two ends of the vacuum chamber and the inner wall of the central collision zone, and a tungsten copper water cooling structure is adopted;
The conventional pulse coil set (3) is a single-turn coil, is axially and symmetrically arranged along the vacuum chamber, is composed of a single-turn coil (10) and N50 nonmagnetic stainless steel (11), is sequentially triggered to generate a transient magnetic field, performs theta pinch, and forms a movable magnetic mirror, captures and pushes a compact ring;
The coil structure of the pulse coil group (4) close to the center is the same as that of the conventional pulse coil group (3), and is a single-turn coil, and the coil material adopts niobium copper or copper-chromium alloy for maintaining fusion reaction of a collision zone;
The superconducting hybrid magnet (5) is arranged in the central collision area and is formed by mixing a high-temperature superconducting magnet and a low-temperature superconducting magnet, a steady-state magnetic cone constraint field is generated, and the central magnetic field is as high as 20T. The magnetic cone field is used for restraining the high-temperature plasma instead of the conductor wall, so that the interaction between the high-temperature plasma and the wall is avoided;
The magnetic mirror holding coil group (6) adopts a multi-turn copper coil design and is symmetrically arranged below the superconducting hybrid magnet (5) to generate a constraint field of tens of milliseconds to maintain fusion reaction;
The low-temperature superconducting reverse magnets (7) are symmetrically arranged at the periphery of the connection part of the outlet of the coaxial gun (1) and the vacuum chamber (2), and the magnetic field intensity at the outlet of the coaxial gun (1) is regulated;
The tritium proliferation cladding (8) surrounds the vacuum chamber (2) and the port of the coaxial gun (1), and all the cladding angles are insulated and cut off, so that the magnetic field permeation is facilitated, and a staggered structure is adopted to avoid neutron leakage;
the power generation module (12) absorbs neutron energy by utilizing the tritium proliferation cladding, converts heat energy into electric energy, and recovers magnetic energy through an electromagnetic induction principle, so that dual-mode power generation of heat energy and magnetic energy is realized.
2. The fusion ignition system based on the compact ring magnetic cone pulse compression technology as set forth in claim 1, wherein the gas injection port (9) of the coaxial gun (1) is filled with deuterium-tritium mixed gas fuel to form high density through high-pressure pulse ionizationA plasma compact ring. The compact ring has both angular and polar magnetic fields, the exit velocity can reach 40 to 400 km/s, and the repetition frequency is not more than 50 Hz.
3. A fusion ignition system based on compact toroid magnetic cone pulse compression technique according to claim 1, characterized in that 30 single turn ring pulse coils are arranged along the axial direction of the vacuum chamber (2), of which 26 are conventional pulse coils (3) and the other 4 are pulse coils (4) near the center, symmetrically distributed on both sides of the collision zone.
4. A fusion ignition system based on compact toroid magnetic cone pulse compression technique according to claim 1, characterized in that the superconducting hybrid magnet (5) has an axial length of 140cm and an inner diameter of 160cm, and can generate a steady-state magnetic field of up to 20T in the collision zone.
5. A fusion ignition system based on compact toroid magnetic cone pulse compression technique according to claim 1, wherein the magnetic mirror holding coil set (6) excites a magnetic field up to 20T, and the magnetic field generated by the superconducting hybrid magnet is superimposed to strengthen and maintain the magnetic mirror for more than 10ms, the total magnetic field being more than 40T.
6. The fusion ignition system based on the compact toroid magnetic cone pulse compression technology according to claim 1, wherein the power generation module (12) realizes efficient recovery of magnetic energy through electromagnetic induction effect of a single-turn loop coil array and a switching circuit.
7. The fusion ignition system based on the compact ring magnetic cone pulse compression technology according to claim 1, wherein the axial length of the vacuum chamber (2) is 8 m, the outer diameter is 38 cm, and the wall thickness of the vacuum chamber is 2 cm. Except the collision area, the vacuum chamber wall adopts vacuum compatible insulating materials such as quartz tubes or silicon carbide fiber reinforced ceramic matrix composite materials, the vacuum chamber wall of the collision area adopts non-magnetic stainless steel materials, the angle is insulated and separated, and tungsten tiles are adopted at the two ends of the vacuum chamber and in the collision area, so that the damage to the vacuum chamber wall caused by high-energy particle bombardment is avoided.
8. The fusion ignition system based on the compact toroid magnetic cone pulse compression technology according to claim 1, wherein the reverse magnetic field strength generated by the low temperature superconducting reverse magnet (7) is 50% -80% of the magnetic field of the superconducting hybrid magnet (5).
9. The fusion ignition system based on the compact ring magnetic cone pulse compression technology according to claim 1, wherein the conventional pulse coil set (3) and the pulse coil set (4) close to the center are single-turn ring coils, and the inner diameter is 40cm, the axial height is 15cm and the radial thickness is 7cm. The conventional pulse coil set (3) adopts a fast discharge capacity power supply mode, the current rising time is 2 mu s, the falling time is 50 mu s, the electrifying current sequentially increases from two ends to the core part, 2-6MA current is supplied, the pulse coil set (4) close to the center adopts an ultra-high voltage power capacitor power supply mode, the current rising time is 2 mu s, the falling time is 1ms, and the electrifying current is 6MA.
10. The fusion ignition system based on the compact ring magnetic cone pulse compression technology according to claim 1, wherein the magnetic mirror holding coil group (6) is 70 cm in inner diameter, 142 cm in outer diameter and 50cm in height, each sub-coil is a multi-turn coil with 360 turns, the coil is powered by a high-voltage power supply, the current rising time is 1ms, the current flat-top maintaining time is >10ms, 10kA current is conducted per turn of the magnetic mirror holding coil group (6), and the magnetic mirror holding coil group (6) compensates the magnetic field drop caused by the four pulse coil groups (4) close to the center in the current dropping period through the time sequence relay of the pulse coil group (4) close to the center, so that the maintenance time of the reinforced magnetic mirror structure exceeds 10 milliseconds to restrain fusion plasma.
11. The fusion ignition system based on the compact ring magnetic cone pulse compression technology of claim 1, wherein the proportion of neutron shielding area of the tritium proliferation cladding (8) is more than or equal to 99.9%, the cladding thickness is 50-80 cm, and tritium self-holding is easy to realize.
12. The fusion ignition system based on the compact toroid magnetic cone pulse compression technology according to claim 1, wherein the coaxial gun (1) can integrate an electron cyclotron heating or neutral beam injection device for preheating and raising the outlet temperature, and the initial speed of the compact toroid is 40-400 km/s.
13. The fusion ignition system based on the compact ring magnetic cone pulse compression technology according to claim 1, wherein the system can also operate in a magnetized target fusion mode, and before the compact rings formed by collision fusion disappear, the compact rings are launched again from two sides, are subjected to cascade compression, impact a magnetized target of a central compact ring, are subjected to axial compression, and are formed into a new compact ring by magnetic reconnection fusion, so that higher fusion three-product parameters are achieved.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202510622954.4A CN120432201B (en) | 2025-05-15 | 2025-05-15 | Fusion ignition system based on compact ring magnetic cone pulse compression technology |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202510622954.4A CN120432201B (en) | 2025-05-15 | 2025-05-15 | Fusion ignition system based on compact ring magnetic cone pulse compression technology |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN120432201A true CN120432201A (en) | 2025-08-05 |
| CN120432201B CN120432201B (en) | 2025-10-24 |
Family
ID=96562972
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202510622954.4A Active CN120432201B (en) | 2025-05-15 | 2025-05-15 | Fusion ignition system based on compact ring magnetic cone pulse compression technology |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN120432201B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN121099510A (en) * | 2025-11-10 | 2025-12-09 | 西南交通大学 | Diagnosis method and system for plasma energy storage in quasi-ring symmetrical star simulator |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2056199A1 (en) * | 1970-11-16 | 1972-05-25 | Genswein A | Fusion reactors - using pinched plasma with laser injection inside spherical magnetic field |
| WO1999016291A1 (en) * | 1997-09-20 | 1999-04-01 | Andrae Juergen | Method for generating energy by controlled plasma-induced nuclear fusion and device for the implementation of said method |
| WO2010093981A2 (en) * | 2009-02-12 | 2010-08-19 | Msnw, Llc | Method and apparatus for the generation, heating and/or compression of plasmoids and/or recovery of energy therefrom |
| WO2013191779A2 (en) * | 2012-03-23 | 2013-12-27 | Princeton Satellite Systems, Inc. | Method, apparatus, and system to reduce neutron production in small clean fusion reactors |
| DE102014002032A1 (en) * | 2014-02-13 | 2015-08-13 | Jochen Otto Prasser | Energy generation by means of thermonuclear fusion and its use for propulsion of spacecraft |
| CN108461160A (en) * | 2018-03-23 | 2018-08-28 | 中国科学院合肥物质科学研究院 | A kind of new ceramics connecting terminal suitable for magnetic confinement nuclear fusion device |
| WO2019055400A1 (en) * | 2017-09-12 | 2019-03-21 | University of New Hamphire | System of converging plasma pistons |
| CN119384702A (en) * | 2022-01-28 | 2025-01-28 | 迈克尔·托马斯·柯申鲁瑟 | Increasing the energy gain in magnetically confined plasmas by increasing the edge temperature: the Super-XT divertor |
| WO2025142890A1 (en) * | 2023-12-25 | 2025-07-03 | 学校法人日本大学 | Mirror fusion device |
| CN120413097A (en) * | 2025-04-30 | 2025-08-01 | 四川合一聚能科技有限公司 | Orthogonal electromagnetic field confinement fusion device and fusion method |
-
2025
- 2025-05-15 CN CN202510622954.4A patent/CN120432201B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2056199A1 (en) * | 1970-11-16 | 1972-05-25 | Genswein A | Fusion reactors - using pinched plasma with laser injection inside spherical magnetic field |
| WO1999016291A1 (en) * | 1997-09-20 | 1999-04-01 | Andrae Juergen | Method for generating energy by controlled plasma-induced nuclear fusion and device for the implementation of said method |
| WO2010093981A2 (en) * | 2009-02-12 | 2010-08-19 | Msnw, Llc | Method and apparatus for the generation, heating and/or compression of plasmoids and/or recovery of energy therefrom |
| WO2013191779A2 (en) * | 2012-03-23 | 2013-12-27 | Princeton Satellite Systems, Inc. | Method, apparatus, and system to reduce neutron production in small clean fusion reactors |
| DE102014002032A1 (en) * | 2014-02-13 | 2015-08-13 | Jochen Otto Prasser | Energy generation by means of thermonuclear fusion and its use for propulsion of spacecraft |
| WO2019055400A1 (en) * | 2017-09-12 | 2019-03-21 | University of New Hamphire | System of converging plasma pistons |
| CN108461160A (en) * | 2018-03-23 | 2018-08-28 | 中国科学院合肥物质科学研究院 | A kind of new ceramics connecting terminal suitable for magnetic confinement nuclear fusion device |
| CN119384702A (en) * | 2022-01-28 | 2025-01-28 | 迈克尔·托马斯·柯申鲁瑟 | Increasing the energy gain in magnetically confined plasmas by increasing the edge temperature: the Super-XT divertor |
| WO2025142890A1 (en) * | 2023-12-25 | 2025-07-03 | 学校法人日本大学 | Mirror fusion device |
| CN120413097A (en) * | 2025-04-30 | 2025-08-01 | 四川合一聚能科技有限公司 | Orthogonal electromagnetic field confinement fusion device and fusion method |
Non-Patent Citations (5)
| Title |
|---|
| JINXING ZHENG: "RECENT PROGRESS IN CHINESE FUSION RESEARCH BASED ON SUPERCONDUCTING TOKAMAK CONFIGURATION", THE INNOVATION, vol. 3, no. 4, 12 June 2022 (2022-06-12) * |
| SHIAO WANG: "MULTI-MODAL FUSION BASED Q-DISTRIBUTION PREDICTION FOR CONTROLLED NUCLEAR FUSION", ADVANCES IN BRAIN INSPIRED COGNITIVE SYSTEMS, 9 March 2025 (2025-03-09) * |
| 曾秋孙;韩运成: "气动磁镜调控关键技术及其在混合核能系统中的应用研究", 2024年度安徽省登记成果2-4月, 31 March 2024 (2024-03-31) * |
| 林木楠: "场反位形等离子体装置的研制", 博士论文, 1 May 2018 (2018-05-01) * |
| 王富甲: "强磁场托克马克环向场线圈应力缓解研究", 核聚变与等离子体物理, vol. 44, no. 01, 12 December 2023 (2023-12-12) * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN121099510A (en) * | 2025-11-10 | 2025-12-09 | 西南交通大学 | Diagnosis method and system for plasma energy storage in quasi-ring symmetrical star simulator |
Also Published As
| Publication number | Publication date |
|---|---|
| CN120432201B (en) | 2025-10-24 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| KR101867092B1 (en) | Efficient compact fusion reactor | |
| Pironti et al. | Fusion, tokamaks, and plasma control: an introduction and tutorial | |
| EP2394496B1 (en) | Systems and methods for compressing plasma | |
| KR101052579B1 (en) | System to drive plasma ions and electrons in an frc magnetic field and method thereof | |
| US6888434B2 (en) | Nuclear fusion reactor incorporating spherical electromagnetic fields to contain and extract energy | |
| US20080226011A1 (en) | Plasma Centrifuge Heat Engine Beam Fusion Reactor | |
| US20110142185A1 (en) | Device for compressing a compact toroidal plasma for use as a neutron source and fusion reactor | |
| JP2017514120A (en) | High efficiency compact fusion reactor | |
| CN120432201B (en) | Fusion ignition system based on compact ring magnetic cone pulse compression technology | |
| WO2010043930A1 (en) | Magnetic and electrostatic nuclear fusion reactor | |
| GB2494185A (en) | A spherical tokamak with toroidal field magnets made from high-temperature superconductor | |
| Jarboe et al. | A proof of principle of imposed dynamo current drive: Demonstration of sufficient confinement | |
| Gusev et al. | The basics of spherical tokamaks and progress in European research | |
| US20070237279A1 (en) | System and method for fusion power generation using very high electrical potential difference | |
| Wilson et al. | The spherical tokamak fusion power plant | |
| Gierszewski et al. | Compact toroid fueling for ITER | |
| US20230106100A1 (en) | Spherical tokamak with high power gain ratio | |
| Gross | Survey of reactor aspects of compact fusion concepts | |
| Robinson | Alternative approaches: concept improvements in magnetic fusion research | |
| Chen | Introduction to controlled fusion | |
| Bongard et al. | Local Helicity Injection Studies on the PEGASUS-III Experiment | |
| Ragheb | Magnetic confinement fusion | |
| Robinson | An Overview of the Physics of Nuclear Fusion: Its Present Status and Future Prospects | |
| Pajączek | Conceptual analysis of a thermonuclear power station with the tokamak type reactor | |
| Hoffman | Field-reversed configurations |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |