Normal-temperature fusion target assembly, laser fusion reactor system and fusion power generation method

By using the fusion target assembly of coaxial compression cone and ignition cone under normal temperature conditions, combined with the laser driving technology with high repetition frequency, the problems of low energy utilization efficiency and low repetition target frequency in the existing technology are solved, and high efficiency is achieved , economical fusion power generation effect.

CN119480160AActive Publication Date: 2025-02-18SHANGHAI JIAOTONG UNIV +2

Patent Information

Application Number
CN202411665249.4
Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Filing Date
2024-11-20
Publication Date
2025-02-18
Estimated Expiration
2044-11-20

AI Technical Summary

Technical Problem

In the prior art, laser indirect drive center ignition scheme is adopted to have problems such as low energy utilization efficiency, low repeated target shooting frequency of deep and low temperature frozen targets, and high fusion power generation cost.

Method used

The normal temperature fusion target assembly is adopted, including a pair of coaxial and cone-top compression cones and ignition cones, through the combined action of high repetition frequency multi-channel high-energy high-power compression laser and ignition laser, the stable compression of fusion fuel and High gain ignition combustion.

Benefits of technology

It has achieved high repetition frequency, low cost and low radioactive fusion power generation to meet the needs of future laser fusion energy applications.

✦ Generated by Eureka AI based on patent content.

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Abstract

The invention provides a normal-temperature fusion target assembly, a laser fusion reactor system and a laser fusion power generation method.The fusion target assembly comprises a pair of coaxial compression cones with opposite cone tops, the compression cones are filled with normal-temperature boron deuteride lithium spherical crown targets, the fusion target assembly further comprises an ignition cone, and the cone tip end of the ignition cone is sleeved with a magnetic field coil; according to the light fusion power generation method, a spherical crown target is driven by compressed laser to generate centripetal implosion, high-density isometric plasma with a steep edge is formed near the sphere center in a collision mode, and tritium production reaction and fusion ignition combustion are generated by the collision plasma under driving of ignition laser. Energy released by high repetition frequency fusion is converted into electric energy which is stably output by a thermodynamic system; the invention further provides a laser nuclear fusion reactor system which is high in repetition frequency, low in cost and low in radioactivity.
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Description

Technical Field

[0001] The present invention relates to the technical field of nuclear power generation, and in particular 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 the laser, Nuckolls in the United States and Wang Ganchang in my country independently proposed the concept of laser nuclear fusion. In 2022, the Livermore National Laboratory in the United States first achieved the net energy gain goal of fusion output energy greater than laser input energy through the central ignition scheme of frozen deuterium-tritium targets. However, this scheme adopts a laser-indirect-driven frozen target central ignition scheme, which inevitably has the characteristics of low laser energy utilization efficiency and strong implosion fluid instability, making it difficult to meet the high efficiency and high repetition rate requirements required for laser fusion power generation.

[0003] In 2018, Chinese scientist Academician Zhang Jie, based on his original idea in 1997 and combined with the latest research progress in recent decades, creatively proposed a double-cone collision ignition scheme. This scheme adopts a fast ignition scheme that separates fuel compression and fusion ignition, and is expected to achieve high-gain fusion ignition with smaller laser energy. Due to factors such as the short research time, the ignition scheme proposed earlier was a single-shot deuterium-tritium frozen 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, low-radioactivity room-temperature target laser fusion power generation method and fusion reactor system that can meet the needs of future laser fusion energy applications. Summary of the invention

[0005] In view of the above-mentioned shortcomings 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, low frequency of repeated target shooting of deep-cryogenic frozen targets and high cost of fusion power generation in the prior art using laser indirect driven central ignition scheme.

[0006] To achieve the above-mentioned purpose and other related purposes, the present invention provides a room-temperature fusion target assembly, the room-temperature fusion target assembly comprising a pair of coaxial compression cones with opposite cone tops, the cone top of each compression cone is cut off and the cone bottom is open, the cone bottom end of each compression cone is filled with a spherical cap target as a fusion fuel, and the protrusion of the spherical cap target points to the cone bottom of the compression cone;

[0007] The room-temperature fusion target assembly also includes an ignition cone, the top 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 top of the ignition cone, and the top of the ignition cone is truncated and sealed, while the bottom of the cone is open.

[0008] The present invention also provides a laser fusion reactor system, comprising the above-mentioned room temperature fusion target assembly and a spherical target chamber, a repetition rate target replacement device, a repetition rate laser device, an online comprehensive diagnosis device, a vacuum device, a fusion energy blanket device, a thermodynamic cycle device and a biological shielding device;

[0009] The repetitive target replacement device is suitable for moving the room temperature fusion target assembly to the center of the spherical target chamber by free fall;

[0010] The repetition rate laser device comprises a compression laser and an ignition laser, wherein the compression laser is suitable for irradiating the spherical cap target from the bottom of the compression cone toward the top of the cone, and the ignition laser is suitable for irradiating from the bottom of the ignition cone toward the top of the cone;

[0011] The online comprehensive diagnostic device is suitable for monitoring the high-frequency laser device, the repetition rate conversion target device and the fusion reaction state;

[0012] The vacuum device is suitable for discharging the rapidly expanding rarefied plasma after the fusion is completed, and maintaining the vacuum degree of the spherical target chamber and the laser transmission channel;

[0013] The fusion energy blanket device is suitable for converting the kinetic energy of neutrons generated by fusion into thermal energy, and is also suitable for providing an additional deuterium and tritium fuel source for the laser fusion power generation system;

[0014] The thermodynamic cycle device comprises a primary loop pipeline, a steam generator and a secondary loop pipeline, and also comprises 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 suitable for connecting to a steam turbine generator through a secondary loop pipeline, and the thermodynamic cycle device is suitable for converting the thermal energy into electrical energy for stable output;

[0015] The biological shielding device is suitable for providing 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 laser fusion reactor system as described above to perform laser fusion power generation, comprising 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. The spherical crown target is imploded by compressed laser ablation, and the two compression cones collide at the coaxial center to form a high-density, isochoric distributed plasma. The ignition laser is irradiated to the ignition cone to generate a high-current neutron, fast electron and thermal electron source, which react with the plasma to produce tritium and ignite and burn, 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 electrical energy with a stable output through a steam turbine generator.

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

[0019] Beneficial effects:

[0020] The invention provides a fusion target assembly, a laser fusion reactor system and a laser fusion power generation method. The fusion target assembly of the invention comprises a pair of coaxial compression cones with opposite cone tops, the compression cones are filled with spherical cap target room temperature fusion fuel (such as lithium deuteride, etc.), and also comprises 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 invention adopts a high repetition frequency multi-channel high energy high power compression laser, and promotes the spherical implosion of the room temperature lithium deuteride fuel placed in the compression cone through laser ablation, and the compressed and accelerated low temperature high Mach number plasma is ejected from the compression cone mouth, collides in the open space between the compression cones, and forms a high density isochoric distribution plasma, and adopts a repetition frequency high energy relativistic intensity ignition laser to form a strong current neutron, fast electron and hot electron source at the bottom of the ignition cone, and forms a high abundance tritium element in the colliding plasma through the tritium formation reaction of neutrons and lithium. With the assistance of the guiding magnetic field, the fast electrons and hot electrons generated by the ignition laser heat the colliding plasma to the ignition and combustion state, releasing a large amount of fusion energy. The energy released by pulsed fusion is converted into stable output electrical energy through a thermodynamic cycle device. In summary, the present invention adopts a double-cone collision ignition scheme to achieve stable compression and high-gain ignition and combustion of room-temperature fusion fuel, and realizes economical, clean and safe thermonuclear fusion power generation through repetitive laser, repetitive target replacement, deuterium-tritium breeding technology and thermodynamic cycle system. BRIEF DESCRIPTION OF THE DRAWINGS

[0021] Figure 1 Schematic diagram of laser-driven ignition of room-temperature fusion target assembly.

[0022] Figure 2 Schematic diagram of the implosion process of fusion fuel driven by compressed laser.

[0023] Figure 3 Schematic diagram of tritium production reaction and fusion ignition driven by ignition laser.

[0024] Figure 4 Schematic diagram of the laser fusion power reactor system.

[0025] Description of Figure Numbers:

[0026] 1. Compression cone; 2. Spherical cap target; 3. Ignition cone; 4. Magnetic field coil; 11. Isovolumetric 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. DETAILED DESCRIPTION

[0027] The following describes the embodiments of the present invention through specific examples, and those skilled in the art can easily understand other advantages and effects of the present invention from the contents disclosed in this specification. The present invention can also be implemented or applied through other different specific embodiments, and the details in this specification can also be modified or changed in various ways based on different viewpoints and applications without departing from the spirit of the present invention.

[0028] In the present invention, unless otherwise clearly specified and limited, the terms "installed", "connected", "connected", "fixed" and the like should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integrated connection; 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, it can be the internal connection of two elements or the interaction relationship between two elements, unless otherwise clearly defined. For ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[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 or after the combination step or the insertion of other method steps between the steps explicitly mentioned, unless otherwise specified. Moreover, unless otherwise specified, the numbering of each method step is only a convenient tool for identifying each method step, and is not intended to limit the order of arrangement of each method step or the scope of the present invention. The change or adjustment of their relative relationship shall also be regarded as the scope of the present invention without substantially changing the technical content.

[0030] It should be noted that the illustrations provided in this embodiment are only used to illustrate the basic concept of the present invention in a schematic manner. Therefore, the drawings only show components related to the present invention rather than being drawn according to the number, shape and size of components in actual implementation. In actual implementation, the type, quantity and proportion of each component may be changed arbitrarily, and the component layout may also be more complicated.

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

[0032] A first aspect of the present invention provides a room temperature fusion target assembly, wherein 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 is cut off and the cone bottom is open, and the cone bottom of each compression cone 1 is filled with a spherical cap target 2 as a fusion fuel, and the protrusion of the spherical cap target 2 points to the cone bottom of the compression cone;

[0033] The fusion target assembly also includes an ignition cone 3, the top 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 coaxial axis of the two compression cones 1, and a magnetic field coil 4 is sleeved at the top of the ignition cone 3, and the top of the ignition cone 3 is truncated and sealed, and the bottom of the cone is open.

[0034] In some embodiments of the present invention, the wall thickness of the compression cone 1 is 20-50 μm, for example, 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, 90°, 100°, 110°, 120°, etc. The opening projection angle in the present invention refers to the cone angle of a cone.

[0036] In some embodiments of the present invention, the radius of the cone top cross section of the compression cone 1 is 40-60 μm, for example 40 μm, 50 μm or 60 μm. In a preferred embodiment of the present invention, the radius of the cone top cross section of the compression cone 1 is 50 μm.

[0037] In some embodiments of the present invention, the distance between the cone tops of the two compression cones 1 is 50-120 μm, for example, 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 cone tops 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 10-30 μm, for example, 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 30-60°, for example, 30°, 40°, 50°, 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 cone top cross section of the ignition cone 3 is 10-30 μm, for example, 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 30-60 μm. For example, 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 cap target 2 is 0.2-2.0 mm, for example, 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 cap target 2 is 100-500 μm, for example, 100 μm, 150 μm, 200 μm, 300 μm, 400 μm, or 500 μm, wherein the thickness refers to the distance between the outer radius and the inner radius of the spherical cap target 2 .

[0044] In some embodiments of the present invention, the cutting edge of the spherical cap target 2 points to the spherical center of the spherical cap target. The spherical center is the vertex of the inner surface of the cone. The cutting edge refers to the fitting surface between the spherical cap target and the inner wall of the compression cone.

[0045] In some embodiments of the present invention, the fusion material of the spherical cap target 2 is selected from one of the room-temperature fusion fuels such as lithium deuteride, lithium borodeuteride or lithium borodeuteride tritide. In a preferred embodiment of the present invention, the fusion material of the spherical cap target is lithium borodeuteride (LiBD4). The role of boron is to soften the energy spectrum of fusion neutrons and absorb the energy of neutrons through elastic scattering, thereby improving the fusion combustion efficiency and the probability of tritium production reaction. The room-temperature fusion spherical cap 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] 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 30-100 μm, for example, 30 μm, 50 μm, 80 μm or 100 μm.

[0048] In some embodiments of the present invention, the material of the compression cone 1 and the ignition cone 3 is selected from a metal having strong X-ray shielding ability such as gold, tungsten, tantalum, etc. The material of the compression cone 1 and the ignition cone 3 can be a metal with good radiation shielding. In a preferred embodiment of the present invention, the material of the compression cone 1 and the ignition cone 3 is gold.

[0049] The second aspect of the present invention provides a laser fusion reactor system, comprising the above-mentioned fusion target assembly 10 and a spherical target chamber, a repetition rate target switching device, a repetition rate laser device 20, an online 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 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;

[0051] The repetition 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;

[0052] The online comprehensive diagnostic device is suitable for monitoring the repetition rate laser device, the repetition rate conversion target device and the fusion reaction state;

[0053] The vacuum device is suitable for discharging the rapidly expanding rarefied plasma after the fusion is completed, maintaining the vacuum environment of the target ball and a clean laser transmission channel; and providing a clean channel for the free propagation of the laser in the target ball;

[0054] The fusion energy blanket device 30 is suitable for converting the neutron kinetic energy generated by fusion into thermal energy, and is also suitable for providing 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 connected to the nitrogen cooling system and the steam generator 42 respectively, the steam generator 42 is suitable for connecting to a steam turbine generator 44 through the secondary loop pipeline 43, and the thermodynamic cycle device is suitable for converting the thermal energy into electrical energy for stable output;

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

[0057] Among them, the kinetic energy of neutrons generated by fusion is converted into thermal energy when it reaches the fusion energy blanket device. The nitrogen in the nitrogen cooling device converts the thermal energy it carries into high-temperature and high-pressure water vapor through the steam generator. 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 city power.

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

[0059] In some embodiments of the present invention, the system further comprises a power generation device, which provides raw power for the laser fusion reactor system.

[0060] In some embodiments of the present invention, the system further comprises an intelligent control device 60, and the intelligent control device 60 is suitable for being electrically connected to the repetition rate target changing device, the repetition rate laser device 20, the online 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 (n+H→D, n+D→T) are generated through the reaction of neutrons and hydrogen elements. The diameter of the ceramic ball is about 1 mm.

[0062] A third aspect of the present invention provides a laser fusion power generation method, which uses the laser fusion reactor system as described above to perform laser fusion power generation, comprising 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, and the spherical cap target 2 is imploded by ablation of the compression laser 21, so that the two compression cones 1 collide at the coaxial center to form a high-density isochoric distributed plasma 11, and 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 plasma to produce tritium and ignite and burn, 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, and the water vapor is converted into stable output electrical energy through a steam turbine generator.

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

[0065] In some embodiments of the present invention, the pulse duration of the compression laser 21 is 5-20 ns, for example, 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 compressed laser 21 is less than 5%, for example, less than 1%, less than 2%, less than 3% or less than 4%.

[0067] In some embodiments of the present invention, the laser power deviation of the compressed laser 21 is less than 5%, for example, less than 1%, less than 2%, less than 3% or less than 4%.

[0068] In some embodiments of the present invention, the pointing accuracy of the laser focal spot center of the compressed 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 cap target 2 is ≥100 terawatts per square centimeter.

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

[0071] In some embodiments of the present invention, the repetition frequency of the ignition laser 22 is ≥ 1 Hz.

[0072] In some embodiments of the present invention, the pulse duration of the ignition laser 22 is 1-20 ps, ​​for example, 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 is ≥ 1×10 20 Watts / square centimeter.

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

[0076] In some embodiments of the present invention, the energy released by each fusion is no less than 5 million joules.

[0077] In some embodiments of the present invention, the fusion output power is no less than 5 megawatts each time.

[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, and the room temperature fusion target assembly 10 undergoes fusion and releases a large amount of energy under the action of the driving laser. Under the action of the fusion energy, the room temperature fusion target assembly debris is first transformed into a high temperature and high pressure plasma gas, and then expands and disperses into a gas with extremely low density in a very short time, and is finally 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 is always kept in a vacuum state during each laser propagation period (about 5 to 20 nanoseconds). The energy released by fusion includes charged particle energy, X-ray photons and neutrons, and these fusion energies are converted into heat energy of the thermodynamic cycle device through the target ball blanket device. The fusion energy blanket system contains abundant hydrogen elements, and can also generate a large amount of deuterium and tritium isotopes (n+H→D and n+D→T) through the reaction of neutrons and hydrogen elements, providing an additional deuterium fusion fuel source for the reactor.

[0079] Example 1

[0080] like Figure 1 As shown, a room temperature lithium borodeuteride spherical crown target 2 is placed in a pair of symmetrically placed compressed gold cones, and a multi-channel compressed laser 21 is uniformly irradiated on the surface of the lithium borodeuteride spherical crown target 2. The ignition gold cone is placed on the side of the compressed gold cone to provide 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 near the top of the ignition gold cone to guide electrons and other charged particles. The wall thickness of the compression gold cone is 30μm, the projection angle of the bottom opening of the compression gold cone is 100°, the distance between the tops of the two compression gold cones is 100μm, the radius of the truncated surface of the tops of the two compression gold cones is 50μm, the outer radius of the spherical cap target is 1200μm, the thickness of the spherical cap target is 300μm, the wall thickness of the ignition gold cone is 10μm, the projection angle of the bottom opening of the ignition gold cone is 30°, the radius of the truncated surface of the top of the ignition gold cone is 15μm, and the distance between the top of the ignition gold cone and the coaxial center point of the compression cone is 40μm.

[0081] When the lithium borodeuteride fuel driven by the compression laser 21 implodes, Figure 2As shown. First, the lithium boron deuteride spherical crown target 2 generates a high-temperature corona plasma that is ejected outward under the irradiation of the compression laser 21. Under the recoil of the corona plasma, the lithium boron deuteride fuel that has not been ablated accelerates and implodes toward the center of the sphere like a spherical rocket. During the implosion process, the density and temperature of the lithium boron deuteride fuel increase rapidly due to the isentropic compression process driven by the compression laser 21. After the high-density lithium boron deuteride fuel generated by the implosion is ejected from the compression gold cone, it continues to slide toward the center of the sphere by inertia until it collides with the lithium boron deuteride fuel ejected from the opposite compression gold cone. During the collision process, the kinetic energy of the lithium boron deuteride fuel is converted into internal energy, and a strong blocking pressure is generated in the collision zone. The temperature and density of the lithium boron deuteride fuel increase rapidly due to the spherical convergence effect and the impact compression effect, forming a high-density isochoric plasma 11 with steep edges, which provides good plasma conditions for the subsequent fast ignition process. During collision, the peak density of lithium borodeuteride fuel is greater than 300g / cc and the surface density is greater than 1g / cm 2 .

[0082] Before the plasma ejects the compressed gold cone, the magnetic field coil 4 with a radius of 50 μm generates a strong axial magnetic field that can guide charged particles, and the peak intensity of the magnetic field is about 1 kilotesla. The strong magnetic field propagates at the speed of light in a vacuum to the vacuum region between the spherical crown targets 2, and then quickly diffuses to the high-resistance lithium boron deuteride spherical crown target 2, and is confined by the high-temperature corona plasma to the area within the high-density spherical crown target. During the compression process, the temperature and implosion velocity of the spherical crown target 2 continue to increase, and the dominant 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 increases rapidly, and the magnetic field in the lithium boron deuteride 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 10,000 Tesla.

[0083] Ignition laser 22 driven tritium production and fusion ignition combustion, such as Figure 3 As shown, a high-energy relativistic picosecond ignition laser 22 of tens of thousands of joules hits the top of the ignition gold cone, generating a large number of high-current neutrons, fast electrons and hot electrons. The high-current neutrons entering the lithium borodeuteride fuel form a high-density deuterium-tritium fuel in the colliding fuel through the tritium reaction (n+Li→T+α). Under the guidance of the magnetic field, the fast electrons and the hot electrons in the high-temperature plasma rapidly heat the deuterium-tritium fuel to the fusion ignition temperature, while generating a large number of neutrons, driving the combustion wave that propagates outward. The neutrons produced by the fusion convert the peripheral lithium borodeuteride fuel into deuterium-tritium fuel, and the newly converted deuterium-tritium fuel achieves deep combustion under the heating of the combustion wave, releasing a large amount of fusion energy. In this implementation example, a single fusion releases at least 10 million joules of energy.

[0084] Example 2

[0085] Laser fusion power generation

[0086] like Figure 4 The schematic diagram of the laser fusion reactor system shown in the figure shows that the diameter of the target sphere is about 10 meters, and the frequency of fusion is 50 times per second. The nuclear-related systems such as the spherical target chamber, the primary circuit pipeline 41 (connected to the nitrogen cooling system) and the steam generator 42 of the secondary circuit pipeline 43 (the steam generator that converts the heat energy carried by helium into high-temperature and high-pressure water vapor and the corresponding pipes, pumps, valves and other components) are contained in a reinforced concrete containment with radiation shielding. Conventional systems such as the heavy-frequency 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 and releases a large amount of energy under the action of the driving laser. Under the action of the fusion energy, the fusion target assembly debris is first transformed into a high-temperature and high-pressure plasma gas, and then expands and disperses into a gas with extremely low density in a very short time, and is finally discharged from the spherical target chamber by the vacuum device. Due to the rapid expansion of fusion debris and the continuous operation of the vacuum device, the laser propagation channel in the spherical target chamber is always kept in a vacuum state during each laser propagation period (about 5 to 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 fusion energy blanket device on the target sphere. The target sphere blanket device contains abundant hydrogen elements, and can also generate a large amount of deuterium and tritium isotopes (n+H→D, n+D→T) through the reaction of neutrons and hydrogen elements, providing an additional source of fusion fuel for the reactor, 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 laser fusion power generation method. The fusion target assembly of the present invention comprises a pair of coaxial compression cones with opposite cone tops, the compression cones are filled with room-temperature lithium borodeuteride spherical crown target materials, and also comprise an ignition cone, and a magnetic field coil is also sleeved on the cone tip of the ignition cone; the laser fusion power generation method of the present invention adopts a double-cone collision ignition scheme to achieve stable compression and high-gain ignition and combustion of room-temperature fusion fuel, and realizes economic, clean and safe thermonuclear fusion power generation through repetitive laser, repetitive target replacement, deuterium breeding technology and thermodynamic cycle system. First, the method realizes isentropic compression and stable collision of fusion fuel through the room-temperature lithium borodeuteride spherical implosion guided by the compression cone and the plasma jet collision between the cones, forming a high-density isochoric plasma with steep edges. Secondly, through the interaction between the high-energy relativistic ignition laser and the ignition cone, a strong current of neutrons and electrons is generated. While tritium is produced by the reaction of neutrons and lithium elements, the fast electrons and hot electrons generated by the ignition laser heat the fusion fuel to the ignition temperature, achieving deep combustion of the fusion fuel and releasing a large amount of fusion energy. Thirdly, the neutrons, charged particles and X-ray energy released by fusion are converted and absorbed by the target ball cladding device, and further enter the thermodynamic cycle device of the reactor. Finally, the steam turbine and the generator convert the energy carried by the thermodynamic cycle device into electrical energy. The high-repetition-rate, low-cost, low-radioactivity room-temperature laser fusion power generation method and laser fusion reactor system proposed by the present invention on the basis of a single-shot frozen target can meet the needs of future laser fusion energy applications. Therefore, the present invention effectively overcomes the various shortcomings of the prior art and has a high industrial utilization value.

[0088] The above embodiments are merely illustrative of the principles and effects of the present invention, and are not intended to limit the present invention. Anyone familiar with the art may modify or alter the above embodiments without departing from the spirit and scope of the present invention. Therefore, all equivalent modifications or alterations made by a person of ordinary skill in the art without departing from the spirit and technical concept disclosed by the present invention shall still be covered by the claims of the present invention.

Claims

1. A room temperature fusion target assembly, characterized in that: 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) is cut off and the cone bottom is open, the cone bottom of each compression cone (1) is filled with a spherical cap target (2) as room-temperature fusion fuel, and the protrusion of the spherical cap target (2) points 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) 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 coaxial axis of the two compression cones (1), a magnetic field coil (4) is sleeved at the cone top of the ignition cone (3), and the cone top of the ignition cone (3) is truncated and sealed, while the cone bottom is open.

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

3. The room temperature fusion target assembly 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 to 60°; And / or, the radius of the cone top cross section of the ignition cone (3) is 10 to 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 to 60 μm.

4. The room temperature fusion target assembly according to claim 1, characterized in that: The outer radius of the spherical cap target (2) is 0.2 to 2.0 mm; And / or, the thickness of the spherical cap target (2) is 100 to 500 μm; And / or, the cutting edge of the spherical cap target (2) points towards the spherical center direction 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 to 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. A laser fusion reactor system, characterized in that: The invention comprises a room temperature fusion target assembly (10) as claimed in any one of claims 1 to 4, as well as 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 repetitive target replacement device is suitable for moving the room temperature fusion target assembly (10) to the center of the spherical target chamber through free fall; The repetition rate 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 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 (2) 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 the neutron kinetic energy generated by fusion into thermal energy, and is also suitable for providing an additional deuterium and tritium fuel source for the 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) is respectively connected to the nitrogen cooling system and the steam generator (42), the steam generator (42) is suitable for connecting to a steam turbine generator (444) through the secondary loop pipeline (43), and the thermodynamic cycle device is 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.

6. The laser fusion reactor system according to claim 5, 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, which is suitable for being 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.

7. A laser fusion power generation method, characterized in that: The laser fusion reactor system according to any one of claims 5 to 6 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 with 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 steep edges. 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, 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 stable output through a steam turbine generator.

8. The laser fusion power generation method according to claim 7, 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 compression laser (21) is 5 to 20 nanoseconds; and / or, the laser energy deviation between different beams of the compression 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.

9. The laser fusion power generation method according to claim 7, 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 microns; And / or, the peak laser intensity of the ignition laser (22) is ≥1×10 20 Watts / square centimeter.

10. The laser fusion power generation method according to claim 7, characterized in that: The repetition frequency of the fusion is not less than 1 time per second; and / or, the energy released by each fusion is not less than 5 million joules; And / or, the fusion output power each time is not less than 5 megawatts.

Citation Information

Patent Citations

  • Laser fusion ignition device and fusion ignition method

    CN111681783A

  • Laser controllable nuclear fusion system and method for realizing energy gain

    CN116543927A

  • Laser fusion pellet based on deuterium and helium fuel and fusion power generation and propulsion system

    CN119811705A

  • Improvements in or relating to nuclear fusion reactors

    GB993174A

  • Plasma Processing Device

    KR1020220121423A

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