Room-temperature Fusion Target Assembly, Laser Fusion Reactor System, and Fusion Power Generation Method

Abstract

The present invention provides a room-temperature fusion target assembly, a laser fusion reactor system, and a laser fusion power generation method. The fusion target assembly of the present invention includes a pair of coaxial compression cones with their cone tips facing each other. The compression cones are filled with room-temperature lithium borodeuteride spherical-cap targets, and further includes an ignition cone, and a magnetic field coil is sleeved on the cone tip of the ignition cone. The laser fusion power generation method of the present invention is to use compression lasers to drive the spherical-cap targets to undergo centripetal implosion, collide near the center of the sphere to form a high-density isochoric plasma with a steep edge, and the colliding plasma undergoes tritium production reactions and fusion ignition combustion under the drive of the ignition laser. The energy released by high-repetition-rate fusion is converted into steadily output electrical energy by the thermodynamic system. The present invention also provides a laser nuclear fusion reactor system with high repetition rate, low cost, and low radioactivity.

Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power generation, and particularly to a room-temperature fusion target assembly, a laser fusion reactor system, and a fusion power generation method. Background Art

[0002] In the 1960s, shortly after the invention of lasers, Nuckolls in the United States and Wang Ganchang in China independently proposed the concept of laser nuclear fusion. In 2022, the Lawrence Livermore National Laboratory in the United States for the first time achieved the goal of net energy gain with fusion output energy greater than laser input energy through the central ignition scheme of a cryogenic deuterium-tritium target. However, this scheme adopts the central ignition scheme of an indirectly driven cryogenic target by lasers, and inevitably has characteristics such as low laser energy utilization efficiency and strong implosion fluid instability, making it difficult to meet the requirements of high efficiency and high repetition rate for laser fusion power generation.

[0003] In 2018, Academician Zhang Jie, a Chinese scientist, based on his original idea in 1997 and combined with the latest research progress in recent decades, creatively proposed the double-cone collision ignition scheme. This scheme adopts a fast ignition scheme in which fuel compression and fusion ignition are separated, and is expected to achieve high-gain fusion ignition with relatively small laser energy. Due to factors such as a relatively short research time, the early proposed ignition scheme was a single-shot deuterium-tritium cryogenic target scheme. This scheme has unique advantages in demonstrating fusion ignition, but there is still much room for improvement in the commercialization of fusion energy.

[0004] Based on the above technical problems, there is an urgent need to develop a high-repetition-rate, low-cost, and low-radioactivity room-temperature target laser fusion power generation method and a fusion reactor system that meet the application requirements of future laser fusion energy. Summary of the Invention

[0005] In view of the above-mentioned disadvantages of the prior art, the purpose of the present invention is to provide a room-temperature fusion target assembly, a laser fusion reactor system, and a fusion power generation method, which are used to solve the problems of low energy utilization efficiency in the prior art using the laser indirect drive central ignition scheme, low repetition rate of deep cryogenic frozen targets for repeated shots, and high costs of fusion power generation.

[0006] To achieve the above object and other related objects, the present invention provides a room-temperature fusion target assembly. The room-temperature fusion target assembly includes a pair of coaxial compression cones with their cone tips facing each other. The truncated openings at the cone tips of each compression cone are open, and the cone bottoms are open. A spherical cap target serving as a fusion fuel is loaded at the cone bottom end of each compression cone, and the protrusion of the spherical cap target points to the cone bottom of the compression cone.

[0007] The room-temperature fusion target assembly further includes an ignition cone. The apex of the ignition cone corresponds to the coaxial center point of the two compression cones, and the central axis of the ignition cone is perpendicular to the coaxial axis of the two compression cones. A magnetic field coil is sleeved at the apex of the ignition cone. The apex of the ignition cone is truncated and sealed, and the bottom of the cone is open.

[0008] The present invention also provides a laser fusion reactor system, including the above-mentioned room-temperature fusion target assembly, a spherical target chamber, a high-repetition-rate target-changing device, a high-repetition-rate laser device, an on-line comprehensive diagnostic device, a vacuum device, a fusion energy blanket device, a thermodynamic cycle device, and a biological shielding device;

[0009] The high-repetition-rate target-changing device is adapted to move the room-temperature fusion target assembly to the center of the spherical target chamber through free fall;

[0010] The high-repetition-rate laser device includes a compression laser and an ignition laser. The compression laser is adapted to irradiate the spherical crown target from the bottom of the compression cone towards the apex direction, and the ignition laser is adapted to irradiate from the bottom of the ignition cone towards the apex direction;

[0011] The on-line comprehensive diagnostic device is adapted to monitor the high-frequency laser device, the high-repetition-rate target-changing device, and the fusion reaction state;

[0012] The vacuum device is adapted to discharge the rapidly expanding rarefied plasma after the fusion ends, and maintain the vacuum degree of the spherical target chamber and the laser transmission channel;

[0013] The fusion energy blanket device is adapted to convert the kinetic energy of neutrons generated by the fusion into heat energy, and is also adapted to provide an additional deuterium-tritium fuel source for the laser fusion power generation system;

[0014] The thermodynamic cycle device includes a primary loop pipeline, a steam generator, and a secondary loop pipeline, and also includes a nitrogen cooling system flowing through the fusion energy blanket device. The primary loop pipeline is respectively connected to the nitrogen cooling system and the steam generator. The steam generator is adapted to be connected to a steam turbine generator through the secondary loop pipeline. The thermodynamic cycle device is adapted to convert the heat energy into smoothly output electric energy;

[0015] The biological shielding device is adapted to provide radioactive shielding for personnel and organisms outside the laser fusion power generation system.

[0016] The present invention also provides a laser fusion power generation method, which uses the above-mentioned laser fusion reactor system for laser fusion power generation, including the following steps:

[0017] The room-temperature fusion target assembly freely falls from the top of the spherical target chamber to the center of the spherical target chamber at a certain interval. Compressed laser ablation is used to implode the spherical-crown target, so that a high-density isochoric distributed plasma is formed by the collision at the coaxial center of the two compression cones. Ignition laser irradiation is used to irradiate the ignition cone to generate a high-current neutron, fast electron, and hot electron source, which undergoes a tritium production reaction and ignition combustion with the plasma to release fusion energy. The fusion energy is converted into heat energy through a nitrogen cooling device, and the heat energy is converted into high-temperature and high-pressure steam in a steam generator. The steam is converted into smoothly output electrical energy through a steam turbine generator.

[0018] As described above, the fusion target assembly, the laser fusion reactor system, and the laser fusion power generation method of the present invention have the following

[0019] Beneficial effects:

[0020] The present invention provides a fusion target assembly, a laser fusion reactor system, and a laser fusion power generation method. The fusion target assembly of the present invention includes a pair of coaxial compression cones with opposite cone tips. The compression cones are filled with spherical-crown target room-temperature fusion fuel (such as lithium borodeuteride, etc.), and also includes an ignition cone, and a magnetic field coil is sleeved on the cone tip of the ignition cone. The laser fusion power generation method of the present invention uses a high-repetition-rate multi-channel high-energy high-power compressed laser. Through the laser ablation effect, the room-temperature lithium borodeuteride fuel placed in the compression cone is spherically imploded. The compressed and accelerated low-temperature high-Mach-number plasma is ejected from the mouth of the compression cone and collides in the open space between the compression cones to form a high-density isochoric distributed plasma. A high-repetition-rate high-energy relativistic-intensity ignition laser is used to form a high-current neutron, fast electron, and hot electron source at the bottom of the ignition cone, and a high-abundance tritium element is formed in the colliding plasma through the tritium production reaction of neutrons and lithium. With the assistance of a guiding magnetic field, the fast electrons and hot electrons generated by the ignition laser heat the colliding plasma to the ignition combustion state, releasing a large amount of fusion energy. The energy released by pulsed fusion is converted into smoothly output electrical energy through a thermodynamic cycle device. In short, the present invention adopts a double-cone collision ignition scheme to achieve stable compression and high-gain ignition combustion of room-temperature fusion fuel, and realizes economical, clean, and safe thermonuclear power generation through high-repetition-rate lasers, high-repetition-rate target replacement, deuterium-tritium breeding technology, and a thermodynamic cycle system. Description of the Drawings

[0021] Figure 1 It is a schematic diagram of laser-driven ignition of a room-temperature fusion target assembly.

[0022] Figure 2 It is a schematic diagram of the implosion process of fusion fuel driven by a compressed laser.

[0023] Figure 3 It is a schematic diagram of tritium production reaction and fusion ignition driven by an ignition laser.

[0024] Figure 4 It is a schematic diagram of a laser fusion power generation reactor system.

[0025] Explanation of the reference numerals in the attached drawings:

[0026] 1. Compression cone; 2. Spherical crown target; 3. Ignition cone; 4. Magnetic field coil; 11. Isochoric plasma; 10. Room-temperature fusion target assembly; 20. Repetitive frequency laser device; 30. Fusion energy blanket device; 40. Thermodynamic cycle device; 50. Biological shielding device; 60. Intelligent control device; 21. Compression laser; 22. Ignition laser; 41. Primary loop pipeline; 42. Steam generator; 43. Secondary loop pipeline; 44. Steam turbine generator. Specific implementation manners

[0027] The following uses specific specific examples to illustrate the implementation manners of the present invention. Those skilled in the art can easily understand other advantages and effects of the present invention from the content disclosed in this specification. The present invention can also be implemented or applied through other different specific implementation manners. Various details in this specification can also be modified or changed based on different viewpoints and applications without departing from the spirit of the present invention.

[0028] In the present invention, unless otherwise clearly defined and limited, terms such as "installation", "connection", "connection", "fixation" and other terms should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral body; it can be a mechanical connection, an electrical connection, or a communication connection; it can be a direct connection, or an indirect connection through an intermediate medium, which can be the internal communication of two components or the interaction relationship between two components, unless otherwise clearly limited. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to specific situations.

[0029] In addition, it should be understood that one or more method steps mentioned in the present invention do not exclude the existence of other method steps before and after the combined steps or the insertion of other method steps between these clearly mentioned steps, unless otherwise stated. Moreover, unless otherwise stated, the numbers of the method steps are only convenient tools for identifying the method steps, rather than limiting the arrangement order of the method steps or the scope in which the present invention can be implemented. The change or adjustment of their relative relationship, without substantial change in the technical content, should also be regarded as the scope in which the present invention can be implemented.

[0030] It should be noted that the illustrations provided in this embodiment only schematically illustrate the basic concept of the present invention. Therefore, only the components related to the present invention are shown in the drawings, rather than being drawn according to the number, shape, and size of the components in actual implementation. The types, quantities, and proportions of the components in actual implementation can be arbitrarily changed, and the component layout type may also be more complex.

[0031] The "apex of the cone" is the tip of the cone. In the present invention, the "apex of the cone" is the end with a smaller bottom area, and the "base of the cone" is the end with a larger bottom area of the cone.

[0032] The first aspect of the present invention provides a room-temperature fusion target assembly. The room-temperature fusion target assembly 10 includes a pair of coaxial compression cones 1 with their apices facing each other. The apex of each compression cone 1 is truncated and open, and the base is open. A spherical cap target 2 as a fusion fuel is loaded at the base end of each compression cone 1, and the protrusion of the spherical cap target 2 points to the base of the compression cone.

[0033] The fusion target assembly further includes an ignition cone 3. The apex of the ignition cone 3 corresponds to the coaxial center point of the two compression cones 1, and the central axis of the ignition cone 3 is perpendicular to the axis of the two compression cones 1. A magnetic field coil 4 is sleeved at the apex of the ignition cone 3, and the apex of the ignition cone 3 is truncated and sealed, and the base is open.

[0034] In some embodiments of the present invention, the wall thickness of the compression cone 1 is 20 - 50 μm. For example, it can be 20 μm, 30 μm, 35 μm, 40 μm, or 50 μm.

[0035] In some embodiments of the present invention, the opening projection angle of the compression cone 1 is 90 - 120°. For example, it can be 90°, 100°, 110°, 120°, etc. The opening projection angle in the present invention refers to the cone angle of the cone.

[0036] In some embodiments of the present invention, the radius of the truncated section at the apex of the compression cone 1 is 40 - 60 μm. For example, it can be 40 μm, 50 μm, or 60 μm. In a preferred embodiment of the present invention, the radius of the truncated section at the apex of the compression cone 1 is 50 μm.

[0037] In some embodiments of the present invention, the distance between the apices of the two compression cones 1 is 50 - 120 μm. For example, it can be 50 μm, 60 μm, 70 μm, 80 μm, 90 μm, 100 μm, 110 μm, 120 μm, etc. In a preferred embodiment of the present invention, the distance between the apices of the two compression cones 1 is 100 μm, etc.

[0038] In some embodiments of the present invention, the wall thickness of the ignition cone 3 is 10 to 30 μm. For example, it is 10 μm, 15 μm, 20 μm, 25 μm, or 30 μm.

[0039] In some embodiments of the present invention, the opening projection angle of the ignition cone 3 is 30 to 60°. For example, it is 30°, 40°, 50°, or 60°. In a preferred embodiment of the present invention, the opening projection angle of the ignition cone 3 is 30°.

[0040] In some embodiments of the present invention, the radius of the cross-section at the apex of the ignition cone 3 is 10 to 30 μm. For example, it is 10 μm, 20 μm, or 30 μm.

[0041] In some embodiments of the present invention, the distance between the apex of the ignition cone and the coaxial center point of the two compression cones is 30 to 60 μm. For example, it is 30 μm, 40 μm, 50 μm, or 60 μm. In a preferred embodiment of the present invention, the distance between the apex of the ignition cone 3 and the coaxial center point of the two compression cones is 50 μm.

[0042] In some embodiments of the present invention, the outer radius of the spherical-crown target 2 is 0.2 to 2.0 mm. For example, it is 0.2 mm, 0.6 mm, 0.8 mm, 1.0 mm, or 2.0 mm.

[0043] In some embodiments of the present invention, the thickness of the spherical-crown target 2 is 100 to 500 μm. For example, it is 100 μm, 150 μm, 200 μm, 300 μm, 400 μm, or 500 μm. Herein, the thickness refers to the distance between the outer radius and the inner radius of the spherical-crown target 2.

[0044] In some embodiments of the present invention, the cutting edge of the spherical-crown target 2 points towards the spherical center direction of the spherical-crown target. The spherical center is the vertex of the inner surface of the cone. Herein, the cutting edge refers to the mating surface between the spherical-crown target and the inner wall of the compression cone.

[0045] In some embodiments of the present invention, the fusion material of the spherical-crown target 2 is selected from one of the room-temperature fusion fuels such as lithium deuteride, lithium borodeuteride, or lithium borodeuterotritide. In a preferred embodiment of the present invention, the fusion material of the spherical-crown target is lithium borodeuteride (LiBD4). The role of boron is to soften the energy spectrum of the fusion neutrons and absorb the energy of the neutrons through elastic scattering, thereby improving the fusion combustion efficiency and the probability of the tritium production reaction. The room-temperature fusion spherical-crown target suitable for fast ignition in the fusion target assembly of the present invention can also be changed to a central ignition target composed of a deuterium-tritium gas bag and a lithium borodeuteride spherical shell.

[0046] Among them, the density of lithium borodeuteride is about 1.0 g / cc.

[0047] In some embodiments of the present invention, the radius of the magnetic field coil 4 is 30 to 100 μm. For example, it is 30 μm, 50 μm, 80 μm or 100 μm.

[0048] In some embodiments of the present invention, the materials of the compression cone 1 and the ignition cone 3 are selected from one of the metals such as gold, tungsten, tantalum, etc. that have strong X-ray shielding capabilities. The materials of the compression cone 1 and the ignition cone 3 can be metals with good radiation shielding. In a preferred embodiment of the present invention, the materials of the compression cone 1 and the ignition cone 3 are gold.

[0049] The second aspect of the present invention provides a laser fusion reactor system, including the above-mentioned room-temperature fusion target assembly 10, a spherical target chamber, a high-repetition-rate target-changing device, a high-repetition-rate laser device 20, an on-line comprehensive diagnostic device, a vacuum device, a fusion energy blanket device 30, a thermodynamic cycle device 40, and a biological shielding device 50;

[0050] The high-repetition-rate target-changing device is adapted to move the room-temperature fusion target assembly 10 to the center of the spherical target chamber by free fall;

[0051] The high-repetition-rate laser device includes a compression laser 21 and an ignition laser 22. The compression laser 21 is adapted to irradiate the spherical crown target 2 from the bottom of the compression cone 1 towards the top of the cone, and the ignition laser 22 is adapted to irradiate from the bottom of the ignition cone 3 towards the top of the cone;

[0052] The on-line comprehensive diagnostic device is adapted to monitor the high-repetition-rate laser device, the high-repetition-rate target-changing device, and the fusion reaction state;

[0053] The vacuum device is adapted to discharge the rapidly expanding rarefied plasma after the fusion is completed, maintain the vacuum environment of the target sphere and a clean laser transmission channel; provide a clean channel for the free propagation of the laser in the target sphere;

[0054] The fusion energy blanket device 30 is adapted to convert the kinetic energy of the neutrons generated by the fusion into heat energy, and is also adapted to provide an additional deuterium-tritium fuel source for the laser fusion power generation system;

[0055] The thermodynamic cycle device 40 includes a primary loop pipeline 41, a steam generator 42, and a secondary loop pipeline 43, and also includes a nitrogen cooling system flowing through the fusion energy blanket device 30. The primary loop pipeline 41 is respectively connected to the nitrogen cooling system and the steam generator 42. The steam generator 42 is adapted to be connected to a steam turbine generator 44 through the secondary loop pipeline 43. The thermodynamic cycle device is adapted to convert the heat energy into smoothly output electrical energy;

[0056] The biological shielding device 50 is adapted to provide radioactive shielding for the personnel and organisms outside the laser fusion power generation system.

[0057] Among them, the kinetic energy of the neutrons generated by fusion becomes heat energy when reaching the fusion energy blanket device. The nitrogen in the nitrogen cooling device converts the carried heat energy into high-temperature and high-pressure water vapor through a steam generator, and the steam turbine generator converts the energy carried by the water vapor into electrical energy, providing an energy source for the power transmission and transformation system connected to the mains.

[0058] In some embodiments of the present invention, the biological shielding device 50 is a reinforced concrete containment.

[0059] In some embodiments of the present invention, the system further includes a power generation device, and the power generation device provides the original power for the laser fusion reactor system.

[0060] In some embodiments of the present invention, the system further includes an intelligent control device 60, and the intelligent control device 60 is adapted to be electrically connected to the high-repetition-rate target conversion device, the high-repetition-rate laser device 20, the on-line comprehensive diagnosis device, and the vacuum device respectively for intelligent regulation.

[0061] In some embodiments of the present invention, the material of the fusion energy blanket device 30 is a ceramic ball containing polyethylene or deuterated polyethylene. This material can be used for neutron moderation, and a large amount of deuterium and tritium elements are generated through the reaction of neutrons and hydrogen elements (n + H → D, n + D → T). The diameter of the ceramic ball is about 1 mm.

[0062] The third aspect of the present invention provides a laser fusion power generation method, which uses the laser fusion reactor system as described above for laser fusion power generation, including the following steps:

[0063] The room-temperature fusion target assembly 10 freely falls from the top of the spherical target chamber to the center of the spherical target chamber at a certain interval. The ablation of the compression laser 21 is used to implode the spherical-crowned target 2, so that a high-density isochoric distributed plasma 11 is formed by the collision at the coaxial center of the two compression cones 1. The ignition laser 22 is used to irradiate the ignition cone 3 to generate a strong-current neutron, fast electron, and hot electron source, which reacts with the plasma to generate tritium and ignite combustion, releasing fusion energy. The fusion energy is converted into heat energy through the nitrogen cooling device, the heat energy is converted into high-temperature and high-pressure water vapor in the steam generator, and the water vapor is converted into smoothly output electrical energy through the steam turbine generator.

[0064] In some embodiments of the present invention, the total energy of the compression laser 21 ≥ 100,000 joules. For example, it is 100,000 joules, 200,000 joules, or 1,000,000 joules.

[0065] In some embodiments of the present invention, the pulse duration of the compression laser 21 is 5 - 20 ns. For example, it is 5 ns, 10 ns, 15 ns, or 20 ns.

[0066] In some embodiments of the present invention, the laser energy deviation between different beams of the compression laser 21 < 5%. For example, it is < 1%, < 2%, < 3% or < 4%.

[0067] In some embodiments of the present invention, the laser power deviation of the compression laser 21 < 5%. For example, it is < 1%, < 2%, < 3% or < 4%.

[0068] In some embodiments of the present invention, the pointing accuracy of the center of the laser focal spot of the compression laser 21 is better than 20 microns.

[0069] In some embodiments of the present invention, the peak laser intensity on the surface of the spherical crown target 2 ≥ 100 terawatts per square centimeter.

[0070] In some embodiments of the present invention, the total energy of the ignition laser 22 ≥ 20,000 joules.

[0071] In some embodiments of the present invention, the repetition rate of the ignition laser 22 ≥ 1 hertz.

[0072] In some embodiments of the present invention, the pulse duration of the ignition laser 22 is 1 - 20 ps. For example, it is 1 ps, 5 ps, 10 ps or 20 ps.

[0073] In some embodiments of the present invention, the diameter of the laser focal spot of the ignition laser 22 is less than 50 microns.

[0074] In some embodiments of the present invention, the peak laser intensity of the ignition laser 22 ≥ 1×10 20 watts per square centimeter.

[0075] In some embodiments of the present invention, the repetition rate of the fusion occurrence is not less than 1 time per second.

[0076] In some embodiments of the present invention, the energy released by each fusion is not less than 5 million joules.

[0077] In some embodiments of the present invention, the output power of each fusion is not less than 5 megawatts.

[0078] In the laser fusion power generation method of the present invention, the room-temperature fusion target assembly 10 moves from the top of the reactor spherical target chamber to the center of the target chamber in a free-fall manner. The room-temperature fusion target assembly 10 undergoes fusion under the action of the driving laser and releases a large amount of energy. The debris of the room-temperature fusion target assembly first turns into a high-temperature and high-pressure plasma gas under the action of the fusion energy, then expands and scatters into a gas with extremely low density in a very short time, and finally is discharged from the spherical target chamber by a vacuum device. Due to the rapid expansion of the fusion debris and the continuous operation of the vacuum device, the laser propagation channel in the spherical target chamber remains in a vacuum state during each laser propagation period (about 5 - 20 nanoseconds). The energy released by fusion includes charged particle energy, X-ray photons, and neutrons. These fusion energies are converted into thermal energy of the thermodynamic cycle device through the target ball cladding device. The fusion energy cladding system contains a rich amount of hydrogen element, and a large amount of deuterium and tritium isotopes can also be generated through the reaction of neutrons and hydrogen elements (n + H → D and n + D → T), providing an additional source of deuterium fusion fuel for the reactor.

[0079] Example 1

[0080] As Figure 1 shown, the room-temperature lithium deuteride spherical cap target 2 is placed in a pair of symmetrically placed compression gold cones, and the multi-channel compression laser 21 irradiates the surface of the lithium deuteride spherical cap target 2 evenly. The ignition gold cone is placed on the side of the compression gold cone, providing an incident channel for the picosecond ignition laser 22. The magnetic field coil 4 is sleeved near the tip of the ignition gold cone, and the circular current flowing through the coil generates an axial magnetic field that guides electrons and other charged particles near the apex of the ignition gold cone. Among them, the wall thickness of the compression gold cone is 30 μm, the projection angle of the bottom opening of the compression gold cone is 100°, the distance between the apices of the two compression gold cones is 100 μm, the radius of the cross-section of the apex of the two compression gold cones is 50 μm, the outer radius of the spherical cap target is 1200 μm, the thickness of the spherical cap target is 300 μm, the wall thickness of the ignition gold cone is 10 μm, the projection angle of the bottom opening of the ignition gold cone is 30°, the radius of the cross-section of the apex of the ignition gold cone is 15 μm, and the distance between the apex of the ignition gold cone and the coaxial center point of the compression cone is 40 μm.

[0081] When the lithium deuteride fuel driven by the compression laser 21 implodes, as Figure 2As shown in the figure. First, the spherical-crown target of lithium borodeuteride 2 generates a high-temperature corona plasma that ejects outward under the irradiation of the compression laser 21. Under the recoil of the corona plasma, the unablated lithium borodeuteride fuel accelerates inward like a spherical rocket towards the center of the sphere. During the implosion process, the density and temperature of the lithium borodeuteride fuel rapidly increase due to the isentropic compression process driven by the compression laser 21. After the high-density lithium borodeuteride fuel generated by the implosion ejects from the compressed gold cone, it continues to slide towards the center of the sphere by inertia until it collides with the lithium borodeuteride fuel ejected from the opposite compressed gold cone. During the collision process, the kinetic energy of the lithium borodeuteride fuel is converted into internal energy, generating a strong blocking pressure in the collision area. The temperature and density of the lithium borodeuteride fuel rapidly increase due to the spherical convergence effect and the shock compression effect, forming a high-density isochoric plasma 11 with a steep edge, providing good plasma conditions for the subsequent fast ignition process. During the collision, the peak density of the lithium borodeuteride fuel is greater than 300 g / cc, and the areal density is greater than 1 g / cm 2 .

[0082] Before the plasma ejects from the compressed gold cone, a strong axial magnetic field that can guide charged particles is generated by the magnetic field coil 4 with a radius of 50 μm. The peak intensity of the magnetic field is about 1 kilotesla. The strong magnetic field propagates in a vacuum at the speed of light to the vacuum area between the spherical-crown targets 2, and then quickly diffuses to the high-resistance spherical-crown target of lithium borodeuteride 2 and is confined in the area within the high-density spherical-crown target by the high-temperature corona plasma. During the compression process, the temperature and implosion speed of the spherical-crown target 2 continuously increase, and the main evolution mechanism of the magnetic field in the spherical-crown target changes from magnetic diffusion to magnetic freezing. During the collision process, the density of the plasma rapidly increases, and the magnetic field in the lithium borodeuteride fuel is further amplified due to the magnetic field freezing effect. In this implementation example, the peak magnetic field intensity during the collision is about 10 kilotesla.

[0083] The tritium production and fusion ignition combustion driven by the ignition laser 22 are as Figure 3 shown. A large-energy relativistic picosecond ignition laser 22 with tens of thousands of joules hits the apex of the ignition gold cone, generating a large number of intense current neutrons, fast electrons, and hot electrons. The intense current neutrons entering the lithium borodeuteride fuel form high-density deuterium-tritium fuel in the colliding fuel through the tritium production reaction (n + Li → T + α). The fast electrons and the hot electrons in the high-temperature plasma, under the guidance of the magnetic field, quickly heat the deuterium-tritium fuel to the fusion ignition temperature, driving a combustion wave that propagates outward while generating a large number of neutrons. The neutrons generated by the fusion convert the surrounding lithium borodeuteride fuel into deuterium-tritium fuel, and the newly formed deuterium-tritium fuel undergoes deep combustion under the heating of the combustion wave, releasing a large amount of fusion energy. In this implementation example, at least 10 million joules of energy is released in a single fusion.

[0084] Example 2

[0085] Laser fusion power generation

[0086] As shown in Figure 4 the schematic diagram of the laser fusion reactor system, the diameter of the target ball is about 10 meters, and the frequency of fusion occurrence is 50 times per second. Nuclear-related systems such as the spherical target chamber, the primary loop pipe 41 (connected to the nitrogen cooling system), and the secondary loop pipe 43 (the steam generator that converts the thermal energy carried by helium into high-temperature and high-pressure steam and corresponding components such as pipes, pumps, and valves) of the steam generator 42 are contained within a reinforced concrete containment with radiation shielding. Conventional systems such as the high-repetition-rate laser device 20, the steam turbine generator 44, the power transmission and transformation device, and the intelligent control device 60 are arranged outside the reinforced concrete containment. The room-temperature fusion target assembly 10 moves from the top of the reactor spherical target chamber to the center of the target chamber in a free-fall manner. The room-temperature fusion target assembly undergoes fusion under the action of the driving laser and releases a large amount of energy. The debris of the fusion target assembly first transforms into a high-temperature and high-pressure plasma gas under the action of the fusion energy, then expands and scatters into a gas with extremely low density in a very short time, and finally is discharged from the spherical target chamber by the vacuum device. Due to the rapid expansion of the fusion debris and the continuous operation of the vacuum device, the laser propagation channel in the spherical target chamber remains in a vacuum state during each laser propagation period (about 5 - 20 nanoseconds). The energy released by fusion includes charged particle energy, X-ray photons, and neutrons. These fusion energies are converted into the thermal energy of the thermodynamic cycle device through the fusion energy blanket device on the target ball. The target ball blanket device contains a rich amount of hydrogen element and can also generate a large amount of deuterium and tritium isotopes through the reaction of neutrons and hydrogen elements (n + H → D, n + D → T), providing an additional source of fusion fuel for the reactor and further reducing the economic cost of fusion fuel.

[0087] In summary, the present invention provides a fusion target assembly, a laser fusion reactor system, and a method for laser fusion power generation. The fusion target assembly of the present invention includes a pair of coaxial compression cones with their cone tips facing each other, and the compression cones are filled with a room-temperature lithium borodeuteride spherical-crown target material. It also includes an ignition cone, and a magnetic field coil is sleeved at the cone tip of the ignition cone. The method for laser fusion power generation of the present invention adopts a double-cone collision ignition scheme to achieve stable compression and high-gain ignition combustion of room-temperature fusion fuel, and through a high-repetition-rate laser, high-repetition-rate target replacement, tritium breeding technology, and a thermodynamic cycle system, realizes economical, clean, and safe thermonuclear power generation. First, this method realizes the isentropic compression and stable collision of fusion fuel through the room-temperature lithium borodeuteride spherical implosion guided by the compression cones and the plasma jet collision between the cones, forming a high-density isochoric plasma with a steep edge. Second, through the interaction between a high-energy relativistic ignition laser and the ignition cone, strong-current neutrons and electrons are generated. While producing tritium through the reaction of neutrons and lithium elements, the fusion fuel is heated to the ignition temperature by the fast electrons and thermal electrons generated by the ignition laser, realizing the deep combustion of the fusion fuel and releasing a large amount of fusion energy. Third, the energy of neutrons, charged particles, and X-rays released by fusion is converted and absorbed by the target ball cladding device and further enters the thermodynamic cycle device of the reactor. Finally, the steam turbine and generator convert the energy carried by the thermodynamic cycle device into electrical energy. Based on a single-shot cryogenic target, the present invention proposes a method for room-temperature laser fusion power generation and a laser fusion reactor system with high repetition rate, low cost, and low radioactivity, which can meet the requirements of future laser fusion energy applications. Therefore, the present invention effectively overcomes various disadvantages in the prior art and has high industrial utilization value.

[0088] The above embodiments are only illustrative of the principles and effects of the present invention and are not intended to limit the present invention. Any person familiar with this technology can modify or change the above embodiments without departing from the spirit and scope of the present invention. Therefore, all equivalent modifications or changes made by those with ordinary knowledge in the technical field without departing from the spirit and technical ideas disclosed by the present invention should still be covered by the claims of the present invention.

Claims

1. A laser fusion reactor system, characterized in that: It comprises a room temperature fusion target assembly (10) and a spherical target chamber, a repetition rate target replacement device, a repetition rate laser device (20), an online comprehensive diagnosis device, a vacuum device, a fusion energy blanket device (30), a thermodynamic cycle device (40) and a biological shielding device (50); The room-temperature fusion target assembly (10) comprises a pair of coaxial compression cones (1) with opposite cone tops, the cone top of each compression cone (1) being truncated and having an opening, and the cone bottom being open, and the cone bottom of each compression cone (1) being filled with a spherical cap target (2) as a room-temperature fusion fuel, and the protrusion of the spherical cap target (2) pointing to the cone bottom of the compression cone (1); the room-temperature fusion target assembly (10) further comprises an ignition cone (3), the cone top of the ignition cone (3) corresponding to the coaxial center point of the two compression cones (1), and the central axis of the ignition cone (3) being perpendicular to the coaxial axis of the two compression cones (1), the cone top of the ignition cone (3) being sleeved with a magnetic field coil (4), the cone top of the ignition cone (3) being truncated and having a sealed opening, and the cone bottom being open; The repetitive target replacement device is suitable for moving the room temperature fusion target assembly (10) to the center of the spherical target chamber by free fall; The repetitive laser device comprises a compression laser (21) and an ignition laser (22), wherein the compression laser (21) is suitable for irradiating the spherical cap target (2) from the bottom of the compression cone (1) toward the top of the cone, and the ignition laser (22) is suitable for irradiating from the bottom of the ignition cone (3) toward the top of the cone; The online comprehensive diagnostic device is suitable for monitoring the repetition rate laser device (20), the repetition rate conversion target device and the fusion reaction state; The vacuum device is suitable for discharging the rapidly expanding rarefied plasma after the fusion is completed, and maintaining the vacuum environment of the spherical target chamber and the clean laser transmission channel; The fusion energy blanket device (30) is suitable for converting neutron kinetic energy generated by fusion into thermal energy, and is also suitable for providing an additional deuterium and tritium fuel source for a laser fusion power generation system; The thermodynamic cycle device (40) comprises a primary-loop pipeline (41), a steam generator (42) and a secondary-loop pipeline (43), and also comprises a nitrogen cooling system flowing through the fusion energy blanket device (30), the primary-loop pipeline (41) being connected to the nitrogen cooling system and the steam generator (42) respectively, the steam generator (42) being suitable for being connected to a steam turbine generator (444) via a secondary-loop pipeline (43), and the thermodynamic cycle device being suitable for converting the thermal energy into electrical energy for stable output; The biological shielding device (50) is suitable for providing radioactive shielding for personnel and organisms outside the laser fusion power generation system.

2. The laser fusion reactor system according to claim 1, characterized in that: The wall thickness of the compression cone (1) is 20-50 μm; And / or, the opening projection angle of the compression cone (1) is 90-120°; And / or, the radius of the truncated surface of the cone top of the compression cone (1) is 40-60 μm; And / or, the distance between the cone tops of the two compression cones (1) is 50-120 μm.

3. The laser fusion reactor system according to claim 1, characterized in that: The ignition cone (3) has a wall thickness of 10 to 30 μm; And / or, the opening projection angle of the ignition cone (3) is 30-60°; And / or, the radius of the cone top cross section of the ignition cone (3) is 10-30 μm; And / or, the distance between the cone top of the ignition cone (3) and the coaxial center point of the two compression cones (1) is 30-60 μm.

4. The laser fusion reactor system according to claim 1, characterized in that: The outer radius of the spherical cap target (2) is 0.2-2.0 mm; And / or, the thickness of the spherical cap target (2) is 100-500 μm; And / or, the cutting edge of the spherical cap target (2) points towards the spherical center of the spherical cap target; And / or, the fusion material of the spherical cap target (2) is selected from one of lithium deuteride, lithium borodeuteride or lithium borodeuteride tritide; And / or, the radius of the magnetic field coil (4) is 30-100 μm; And / or, the material of the compression cone (1) and the ignition cone (3) is selected from one of gold, tungsten and tantalum.

5. The laser fusion reactor system according to claim 1, characterized in that: The biological shielding device (50) is a reinforced concrete containment shell; And / or, the system further comprises a power generation device, wherein the power generation device provides original power for the laser fusion reactor system; And / or, the system further comprises an intelligent control device, wherein the intelligent control device is adapted to be connected to the repetitive target changing device, the repetitive laser device (20), the online comprehensive diagnosis device, and the vacuum device, respectively, to perform intelligent control; And / or, the material of the fusion energy blanket device is a ceramic ball containing polyethylene or deuterated polyethylene.

6. A laser fusion power generation method, characterized in that: The laser fusion reactor system according to any one of claims 1 to 5 is used to perform laser fusion power generation, comprising the following steps: The room temperature fusion target assembly (10) freely falls from the top of the spherical target chamber to the center of the spherical target chamber at a certain interval, and the spherical cap target (2) is imploded by ablation using a compression laser (21), so that the two compression cones (1) collide at the coaxial center to form a high-density isochoric plasma (11) with a steep edge. The ignition laser (22) is used to irradiate the ignition cone (3) to generate a high-current neutron, fast electron and thermal electron source, which react with the isochoric plasma (11) to produce tritium and ignite and burn, thereby releasing fusion energy. The fusion energy is converted into heat energy through a nitrogen cooling device, and the heat energy is converted into high-temperature and high-pressure water vapor in a steam generator. The water vapor is converted into electric energy with a stable output through a steam turbine generator.

7. The laser fusion power generation method according to claim 6, characterized in that: The total energy of the compressed laser (21) is ≥ 100,000 joules; and / or, the repetition frequency of the compressed laser (21) is ≥ 1 Hz; And / or, the pulse duration of the compressed laser (21) is 5 to 20 nanoseconds; and / or, the laser energy deviation between different beams of the compressed laser (21) is less than 5%; and / or, the laser power deviation of the compression laser (21) is less than 5%; and / or the pointing accuracy of the laser focal spot center of the compressed laser (21) is better than 20 microns; And / or, the peak laser intensity on the surface of the spherical cap target (2) is ≥100 terawatts per square centimeter.

8. The laser fusion power generation method according to claim 6, characterized in that: The total energy of the ignition laser is ≥ 200,000 joules; and / or, the repetition frequency of the ignition laser (22) is ≥ 1 Hz; and / or, the pulse duration of the ignition laser (22) is 1 to 20 picoseconds; and / or, the diameter of the laser focal spot of the ignition laser (22) is less than 50 micrometers; and / or the peak laser intensity of the ignition laser (22) is ≥ 1×10 20 Watts / cm2.

9. The laser fusion power generation method according to claim 6, characterized in that: The repetition rate of fusion is not less than 1 time per second; and / or, the energy released per fusion reaction is not less than 5 million joules; and / or, the fusion output power per event is not less than 5 MW.

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