264 results about "Nuclear fusion" patented technology

The invention relates to the technical field of nuclear fusion devices, and discloses a nuclear fusion device and a monitoring system and an installation method thereof, the monitoring system comprises a cold shield main body, the cold shield main body is of an annular rotation structure, and the cold shield main body is arranged in a cavity and wraps the circumferential outer side of a vacuum chamber; the cold shield main body comprises a plurality of groups of fan-shaped cold shield sections which are sequentially arranged in the circumferential direction, and the plurality of groups of fan-shaped cold shield sections are encircled to form the cold shield main body; the distance measuring assembly is arranged on the cold shield main body, the distance measuring assembly comprises a plurality of groups of distance measuring sensors which are arranged in the circumferential direction of the cold shield main body at intervals, and each group of distance measuring sensors comprises a plurality of distance measuring sensors; the distance measuring sensor is used for detecting the size of a gap between the cold shield body and the longitudinal field coil and the size of a gap between the cold shield body and the vacuum chamber. Therefore, the cold shield main body can be assisted to be assembled at a position in the nuclear fusion device, and the matching position of the cold shield main body, the vacuum chamber and the longitudinal field coil can be monitored in real time.

The invention discloses a processing method of a fusion device, and belongs to the technical field of nuclear fusion. The processing method comprises the following steps: carrying out at least one time of vacuum heat treatment on a Dewar embedded part blank; carrying out cleaning anti-corrosion treatment and physical correction treatment on the surface of the dewar embedded part blank subjected to heat treatment; carrying out grinding and polishing treatment on the surface of the Dewar embedded part blank subjected to the cleaning and antiseptic treatment and the physical correction treatment to obtain the Dewar embedded part; the Dewar embedded part is transported to the installation position of the window to be installed, and the Dewar embedded part located at the installation position is temporarily fixed; performing concrete pouring on the mounting position of the Dewar embedded part; and after the concrete is solidified, a cast-in-place concrete structural body is formed in the area below the Dewar embedded part, and a part of the Dewar embedded part is embedded into the cast-in-place concrete structural body. By means of the method, the magnetic conductivity of the Dewar embedded part is reduced, and the risk that elements are activated to form isotopes with the long decay period and the high irradiation dose rate or isotopes with the short decay period and the high irradiation dose rate is reduced.

The invention relates to the technical field of nuclear fusion, and discloses a supporting device and a method for assembling a vacuum chamber and a cold shield of a nuclear fusion device.The supporting device comprises a first supporting assembly and a second supporting assembly, the first supporting assembly comprises a first clamping piece, a first supporting piece and a first adjusting piece, and the first clamping piece and the first supporting piece are spaced in the first direction and connected through the first adjusting piece; the first adjusting piece can adjust the distance between the first clamping piece and the first supporting piece in the first direction. The second supporting assembly comprises a second clamping piece, a second supporting piece and a second adjusting piece, the second clamping piece and the second supporting piece are spaced in the first direction and connected through the second adjusting piece, and the second adjusting piece can adjust the distance between the second clamping piece and the second supporting piece in the first direction; the third adjusting piece is connected with the first supporting piece and the second clamping piece and can adjust the distance between the first supporting piece and the second clamping piece in the first direction. The cold shield and the vacuum chamber can be clamped, and the gap between the cold shield and the vacuum chamber can be adjusted.

The invention relates to the field of nuclear fusion device installation, and discloses a supporting device of a nuclear fusion device preassembled assembly, and the supporting device of the nuclear fusion device preassembled assembly comprises a first supporting section, a second supporting section and an adjustable supporting section which are detachably connected in sequence along a first direction; the adjustable supporting section comprises a first adjusting part, a second adjusting part and a lifting part which are sequentially connected in the first direction, the first adjusting part is connected with the second supporting section and can drive the second adjusting part to be adjusted in the second direction, the second adjusting part can drive the lifting part to be adjusted in the third direction, and the lifting part can be adjusted in the first direction in a lifting mode. The first direction, the second direction and the third direction are perpendicular to one another. The supporting device of the preassembled assembly of the nuclear fusion device can support the bottom of the preassembled assembly, the position precision of the preassembled assembly can be improved, and the installation reliability of the nuclear fusion device is improved.

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The invention relates to the field of nuclear fusion devices, and discloses a fastening device and a mounting structure of a fusion reactor divertor system heat sink structure, and the fastening device of the fusion reactor divertor system heat sink structure is used for connecting the heat sink structure and a main body structure, and comprises a first connecting piece, a supporting disc, a second connecting piece, a first elastic piece and a third connecting piece, a first thread part is arranged on the outer side of the first connecting piece; the supporting disc is arranged in the first groove and is in clearance arrangement with the peripheral groove wall of the first groove; the second connecting piece penetrates through the second hole and is provided with a third groove; the first elastic piece is arranged in the second groove and elastically abuts against the skirt edge part. And the third connecting piece is arranged in the third groove and is in clearance arrangement with the peripheral groove wall of the third groove. A thermal expansion deformation space is reserved in the fastening device of the fusion reactor divertor system heat sink structure, damage to internal parts can be avoided, and the reliability of the fastening device of the fusion reactor divertor system heat sink structure is improved.

The invention relates to the technical field of nuclear fusion, and discloses a vacuum chamber cold shield module and a vacuum chamber cold shield for a nuclear fusion device.The vacuum chamber cold shield module comprises two panel assemblies and a cooling assembly, the two panel assemblies are arranged in the polar direction, and each panel assembly comprises an inner side panel assembly and an outer side panel assembly; the inner side panel and the outer side panel assembly surround a circle in the annular direction, the outer side panel assembly comprises a first outer side panel and a second outer side panel which are arranged in the polar direction, each panel assembly is correspondingly provided with two cooling assemblies, one cooling assembly surrounds the periphery of the first outer side panel and the periphery of the inner side panel in the annular direction, and the other cooling assembly surrounds the periphery of the second outer side panel in the polar direction. The other cooling assembly surrounds the periphery of the second outer side panel and the periphery of the inner side panel in the annular direction, each cooling assembly comprises a plurality of cooling pipelines, the cooling pipelines are arranged at intervals in the polar direction, and the cooling pipelines are filled with cooling media. The vacuum chamber cold shield module for the nuclear fusion device is convenient to mount, high in heat shielding efficiency and uniform in heat transfer performance.

The invention discloses a multi-mode magnetic field intelligent closed-loop plasma confinement system and method. The system comprises a multi-mode magnetic field generation module, a multi-dimensional plasma diagnosis module and a layered intelligent closed-loop control module. The multi-mode magnetic field generation module generates a steady-state, pulse and alternating composite magnetic field to realize adjustable space gradient; the multi-dimensional diagnosis module synchronously acquires electrical, optical and particle parameters, and ensures the accuracy through data fusion; and the hierarchical intelligent closed-loop control module generates an adjusting instruction to realize closed-loop optimization based on dynamic threshold and multi-algorithm scheduling. According to the method, the constraint performance is improved through the steps of initialization, data acquisition, state evaluation and closed-loop adjustment in combination with parameter self-optimization and three-level fault protection. According to the scheme, the plasma constraint time exceeds 300 s, the escape rate is lower than 5%, the adjustment response is smaller than or equal to 10 ms, the method adapts to multiple working conditions and can be popularized to the fields of nuclear fusion experiments and plasma processing, and the problems that a traditional system is poor in stability and lags in response are solved.

The invention provides an orthogonal electromagnetic field confinement fusion device and a fusion method. The fusion device comprises a vacuum combustion furnace which comprises a fusion reaction chamber and an inductance tube; the central shaft is arranged in the vacuum combustion furnace in a penetrating manner, a constant potential difference is applied between the inner wall of the vacuum combustion furnace and the central shaft, and a radial polarization electric field is generated in the vacuum combustion furnace; the inductance coil is wound on the outer wall of the vacuum combustion furnace, generates an axial confinement magnetic field in the vacuum combustion furnace and generates a magnetic mirror in the fusion reaction chamber; the fusion method comprises the following steps: S1, constructing an orthogonal electromagnetic field; s2, feeding fuel; s3, radially polarizing the ion ring; s4, induction of FRC is carried out; s5, axial fusion is carried out; s6, energy recovery; the device has the effects of simplifying the nuclear fusion reaction device, reducing the cost of the nuclear fusion reaction and improving the efficiency of the nuclear fusion reaction.

The invention provides an energy gradient utilization steam Rankine cycle power generation system and method for nuclear fusion, and belongs to the field of nuclear fusion energy conversion and utilization. Different temperature heat of a cladding, a divertor and a vacuum chamber is guided into a high-temperature independent heat storage loop, a medium-temperature independent heat storage loop and a low-temperature independent heat storage loop respectively, an operation section stores heat, and a pause section releases heat; feed water is heated step by step through a multi-stage preheater, an evaporator and a superheater according to the sequence of low temperature, medium temperature and high temperature, and superheated steam of 550 DEG C is formed to continuously drive a turbine to generate power. Decoupling of intermittent output of the fusion reactor and continuous operation of the power generation system is achieved, steam extraction of a steam turbine is omitted, the structure is simplified, and the energy utilization rate and the circulation efficiency are improved.

The present invention provides an appealing, fast, and cost-effective alternative to conventional nuclear fusion reactors. An ultra-compact spherical tokamak that combines three key features aimed at accelerating fusion energy as a viable energy source, these features are spherical type tokamaks, negative triangularity plasma shape and high-temperature superconducting coils. More specifically, the tokamak includes a toroidal vacuum vessel and a magnetic field system configured to confine a high temperature plasma. The magnetic field system includes a solenoid having a sand-hourglass shape; toroidal field coils having an inverse D-shaped design and high temperature superconductor (HTS) material; and poloidal field coils, external to the vacuum vessel. The vacuum vessel has a cross-section with similar inverse D-shape as the toroidal field coils.

The invention discloses a transfer device and a transfer method for transferring a polar field coil of a nuclear fusion device, and relates to the technical field of transfer of parts of the nuclear fusion device. The transfer device comprises a moving mechanism, a supporting mechanism, a supporting piece and a limiting piece, the supporting mechanism is fixedly arranged on the moving mechanism, and a supporting arm is formed on the supporting mechanism; the supporting pieces are in one-to-one correspondence with the supporting arms, each supporting piece is movably arranged in the extending direction of the corresponding supporting arm, and a clamping cavity used for containing at least part of the polar field coil is defined in each supporting piece; the limiting pieces correspond to the supporting arms one to one, each limiting piece is arranged on the corresponding supporting arm, the limiting pieces and the supporting pieces are connected through adjusting pieces, and the adjusting pieces are used for adjusting the distance between the supporting pieces and the limiting pieces. According to the transfer device, the transfer requirements of the polar field coil with large size, heavy weight and strict requirements can be met, it is guaranteed that the polar field coil is accurate in pose and reasonable in stress in the transfer process, and the requirements of the dynamic load coefficient and the unbalance load coefficient are met.

The invention provides an attractive, fast and cost-effective alternative method for conventional nuclear fusion reactors. An ultra-compact spherical Tokamak which combines three key features intended to accelerate fusion energy as feasible energy sources, the features being a spherical Tokamak, a negative triangle plasma shape and a high temperature superconductor coil.

The invention discloses a central column tool for general assembly of a nuclear fusion device host, and belongs to the technical field of nuclear fusion. The center column tool comprises a center column body which is installed in the center of a foundation pit and used for being connected with a center column embedded part located in the center of the foundation pit; the supporting parts are distributed in the circumferential direction of the center column body at intervals and used for being connected with wall embedded parts. The annular field sleeve annular rail is arranged around the central column body and is mounted on the supporting part; the supporting cross beams are distributed in the circumferential direction of the center column body at intervals, and the supporting cross beams are installed between the adjacent supporting parts; the non-standard fan-shaped section radial beams and the standard fan-shaped section radial beams are alternately distributed in the circumferential direction of the center column body at intervals, one ends of the non-standard fan-shaped section radial beams and the standard fan-shaped section radial beams are connected with the center column body, and the other ends of the non-standard fan-shaped section radial beams are connected with the supporting cross beams; and the circumferential field radial beam is rotatably mounted at the top end of the central column body. The general assembly of the main engine of the nuclear fusion device is carried out through the central column tool, and the general assembly efficiency can be remarkably improved.

The invention discloses a coil shielding structure for a linear magnetic confinement nuclear fusion device, and relates to the technical field of nuclear fusion reactors. Comprising a first shielding layer made of a metal material and capable of coating a coil conductor in an insulating manner; and the second shielding layer is made of a metal material and is coated outside the first shielding layer, and an outer cold flow channel is arranged between the second shielding layer and the first shielding layer. The multiple shielding layers are arranged in a laminated mode, electromagnetic wave conduction can be hindered by consuming electromagnetic energy for multiple times, eddy currents generated by a variable magnetic field on coil conductors (quasi-steady-state and cusped coils) are reduced, temperature rise of the coils is reduced, the current-carrying capacity of the coils is improved, the thickness of the shielding layers can be designed to be very thin, and the shielding layers are not prone to deformation. While the eddy current is reduced, the design cost of a conductor material and the self mass of a magnet system are reduced, and meanwhile, the second shielding layer can serve as a stress part to reinforce the mechanical structural strength of the magnet and prevent electromagnetic force from directly acting on a magnet coil to influence the established structure of the magnet coil.

Disclosed herein are methods, systems, media, and techniques for training machine learning models to generate nuclear fusion reactor configurations. Further disclosed herein are systems, methods, computer-readable media, and techniques for configuring a stellarator, including: (a) obtaining one or more parameters of a target stellarator; (b) generating a plurality of target stellarator approximations based at least in part on the one or more parameters of the target stellarator, wherein at least a subset of the plurality target stellarator approximations: (i) have a toroidal profile, and (ii) comprise a plurality of concentric toroids; and (c) presenting at a graphical user interface a representation of the plurality of target stellarator approximations.

The invention provides a multi-heat-source combined energy storage and auxiliary heating system and method for a nuclear fusion device, and belongs to the field of energy conversion and utilization of the nuclear fusion device, and the system comprises a high-temperature heat source storage and supply system which is used for receiving and storing heat of a cladding and a multiplication region coolant, and continuously outputting a high-temperature heat source during the operation and pause of a fusion reactor; the medium-temperature heat source and auxiliary supply system is used for receiving the heat of the divertor coolant and supplementing and outputting the medium-temperature heat source through a medium-temperature auxiliary heater during the suspension period of the fusion reactor; the low-temperature heat source and auxiliary supply system is used for receiving heat of the vacuum chamber coolant and supplementing and outputting a low-temperature heat source through a low-temperature auxiliary heater during the suspension period of the fusion reactor; the high-temperature heat source storage and supply system, the medium-temperature heat source and auxiliary supply system and the low-temperature heat source and auxiliary supply system operate independently. According to the invention, high-temperature heat, medium-temperature heat and low-temperature heat are simultaneously, continuously and stably supplied to the outside during operation and pause of the fusion reactor.

A plasma generation system (10), and a nuclear fusion reaction system and method. The plasma generation system (10) comprises: a plasma generation assembly (101) and a motion assembly (102) connected to the plasma generation assembly (101), wherein the motion assembly (102) is configured to drive the plasma generation assembly (101) to move in a target direction; and the plasma generation assembly (101) is configured to emit plasma once same moves to a target position. The plasma generation system (10) can be used in a nuclear fusion reaction chamber (20) to generate a plasma ring therein, thereby reducing the difficulty in generating a plasma ring in the nuclear fusion reaction chamber (20), and thus improving the effect of a nuclear fusion reaction.

A renewable wall of a fusion reactor chamber is disclosed. In some embodiments of the disclosed technology, a fusion reactor device comprises a fusion reactor chamber including an inner wall that is at least partially made of a wall-forming aggregate to be exposed to a heat flux in the fusion reactor chamber during a nuclear fusion reaction which decomposes into constituent pebbles upon this heat flux exposure, a material collection system structured to collect via gravity, from the inner wall of the fusion reactor, a material recovery unit connected to the material collection system to recover the decomposed wall-forming material and provide a recovered wall-forming material to a wall-forming material container, and an array of extrusion channels connected between the inner wall and the wall-forming material container to feed the recovered wall-forming material from the wall-forming material container toward the inner wall of the fusion reactor chamber.

The invention discloses an equivalent shear force detection system for a nuclear fusion superconducting coil under a multi-element coupling working condition, and belongs to the field of conductor insulation development of the nuclear fusion superconducting coil. The system comprises a nuclear magnetic resonance scanner, a signal exchanger, a liquid helium cooling system, a superconducting coil immersed curing insulation composite material sample piece, a four-stage magnetic field, a bipolar magnetic field, a neutron irradiation probe, a liftable rotary mechanical arm and an AI large model processing server. Completing the detection of the equivalent shearing force of the superconducting coil insulating material under the working conditions of magnetic coupling, neutron irradiation and the like in the nuclear fusion reaction stage; the insulation material equivalent shear force detection system can detect the endogenous organization structure change of the insulation composite material of the superconducting coil in the nuclear fusion reaction stage, and can avoid the situation that the electric insulation composite material of the superconducting coil is forced to be interrupted in the nuclear fusion reaction due to fatigue damage caused by concentrated equivalent shear force.

This invention discloses a firecracker-style controlled nuclear fusion and fission synergistic power generation device and method. The power generation device includes a fission-fusion reaction system, a circulating cooling system, and other accessories. The fission-fusion reaction system includes a neutron gun, fuel spheres, a fuel sphere storage and delivery device, and a vacuum reactor. The circulating cooling system includes a circulating fan, a voltage regulator, a steam turbine, a steam generator, delivery pipelines, and a water pump. Other accessories include an energy storage and control system and a vacuum pump. This invention innovatively integrates the start-up mechanism, drawing on the firecracker-style multi-reactor relay concept, combining nuclear fission and nuclear fusion. It utilizes the high temperature and pressure generated by nuclear fission to start nuclear fusion, reducing start-up difficulty and cost. Simultaneously, it efficiently converts and utilizes energy, employing helium for heat transfer. Helium's high thermal conductivity, low density, high specific heat capacity, and chemical inertness allow it to effectively carry away the heat stored in the phase change microspheres, comprehensively collecting and converting nuclear reaction heat energy, thus improving energy conversion efficiency.

Arrangement (26) for generating EUV radiation or for operating nuclear fusion by irradiating a target material (28) with a plurality of laser beams (20, 22, 24). The arrangement (26) comprises a target chamber (32) having an interior (34) with a target area (36) for irradiating the target material (28) with the plurality of laser beams (20, 22, 24), an insertion device (38) for introducing the target material (28) into the target area (36), and a manipulation device (46) for shaping and / or positioning the target material (28) in the target area (36).

The invention relates to the technical field of nuclear fusion, and provides a supporting structure and a nuclear fusion device. The supporting structure comprises a first connecting assembly, a second connecting assembly, a first supporting assembly and a second supporting assembly. The first connecting assembly is connected with a lower window of the vacuum chamber; the second connecting assembly is connected with the fixed foundation; the first supporting assembly is supported between the first connecting assembly and the second connecting assembly, the first supporting assembly comprises two sets of hinge structures, and the two sets of hinge structures are arranged side by side in the radial direction of the vacuum chamber and are configured into different specifications; the second supporting assembly is supported between the first connecting assembly and the second connecting assembly and comprises two sets of elastic plate arrays, and the two sets of elastic plate arrays are arranged on the two sides of the first supporting assembly in the radial direction of the vacuum chamber. The supporting structure disclosed by the invention not only can stably bear the load of the vacuum chamber in the vertical direction, but also allows the vacuum chamber to generate smaller radial displacement due to baking, and can play a role in stably supporting the vacuum chamber.

The invention relates to the technical field of nuclear fusion device installation, and discloses a central column assembly for a nuclear fusion device, and the central column assembly comprises a main body part which is internally provided with a main body space; the Dewar base is located at the bottom of the main body space; the central column bottom plate is positioned at the bottom of the Dewar base and is connected with the main body part in a leveling manner; the bottom of the central column main body is fixedly connected with the central column bottom plate, a rotatable rotating part is formed at the top of the central column main body, and the central column main body is detachably connected with the Dewar base; wherein the central column main body is constructed into at least two sections of split columns in the axial direction, and at least two adjacent sections of split columns are detachably matched with each other. The central column assembly for the nuclear fusion device is higher in precision, richer in adjusting function and good in structural reliability.

A radiation device comprises at least a vacuum chamber (1), an electromagnetic accelerator (8) for generating a primary energy beam of ions inside the vacuum chamber (1), and a layer of material (S) carried by a support (4) rotating in the vacuum chamber (1) to generate a flow of particles when a series of nuclear fusion reactions are triggered on the material (S) thanks to the energy of said beam, and wherein the support (4) is hollow and sealed defining a rotating three-dimensional surface that surrounds a containment volume for a cooling liquid in heat exchange with the layer of material (S), such rotating three-dimensional surface defining a heat exchange surface wetted by the liquid, and wherein a level of the free surface of the liquid on the heat exchange surface moves upwards in use due to the action of the centrifugal acceleration generated by the rotation of the support (4).

The invention discloses an equipment reliability test method and system and electronic equipment, and relates to the technical field of nuclear fusion. The method comprises the steps that a first magnetic field intensity of a first steady-state magnetic field and a second magnetic field intensity of a first transient magnetic field are obtained according to the installation position of equipment to be tested, and the first steady-state magnetic field and the first transient magnetic field are magnetic fields generated by a nuclear fusion device at the installation position; obtaining a magnetic field intensity threshold according to the first magnetic field intensity or the second magnetic field intensity And carrying out reliability test on the to-be-tested equipment according to the magnetic field intensity threshold to obtain a reliability test result. Therefore, the reliability of the equipment in the nuclear fusion environment can be tested.

The invention discloses a fusion ignition system based on a compact ring magnetic cone pulse compression technology, and belongs to the technical field of nuclear fusion energy. According to the system, high-speed and high-density compact ring plasma is generated through a symmetrical coaxial gun and injected into a vacuum chamber, cascade theta pinch is triggered by a single-turn ring array, the angular current and the magnetic field of a compact ring are enhanced, a moving magnetic mirror structure is formed by combining a superconducting steady-state magnetic cone, inclination instability is restrained, and the compact ring is pushed to a central collision area. After the compact rings on the two sides are collided and fused, the central magnetic mirror holding coil assembly provides slow theta pinch to maintain fusion conditions, and the plasma density gt is achieved; 1023 / m < 3 > and the ion temperature gt; 15 keV, and energy constraint time gt; and the Lawson criterion is met. The system can be switched to a magnetizing target fusion mode, and axial compression and magnetic reconnection fusion are carried out by impacting a magnetizing target through a secondary compact ring. The power generation module adopts cladding and electromagnetic induction dual-mode energy recovery. The technology has the advantages of compact structure, low cost, convenience in maintenance and the like, and provides a new way for commercial fusion power generation.

The invention relates to the design, configuration and operation concept of a system, herein called radioisotope recovery system, to deploy and recover different precursor materials into and from the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of D and T ions, which will cause the generation of radioactive isotopes (also called radioisotopes). Main characteristics of the invention are (i) a closed loop that circulates precursor materials into and out of a nuclear fusion tokamak with beam-driven plasma, (ii) the compliance of the system with the design and maintenance of a nuclear fusion tokamak with beam-driven plasma.

The invention discloses a detection device for a fusion reactor host radiation area, and the device comprises a guide rail assembly which is disposed in a to-be-detected area, and the guide rail assembly covers all detection points in the to-be-detected area. A moving frame is further arranged on the guide rail assembly, and a driving module used for driving the moving frame to move to a target detection point position is further arranged between the moving frame and the guide rail assembly; the detection device further comprises a measuring module and a control module, the measuring module is arranged on the moving frame, and the control module is electrically connected with the driving module and the measuring module. A complete conveying system is constructed in the to-be-detected area of nuclear fusion through the guide rail assembly, a worker can convey the measurement module to a target detection point position through movement of the moving frame according to actual needs and complete detection, automatic and unmanned operation is achieved, potential safety hazards caused by radiation can be reduced, and the detection efficiency is improved. And meanwhile, the data acquisition difficulty can be effectively reduced, and the data acquisition efficiency can be improved.

The invention reduces the energy level of fast-ignation lasers required for whispering gallery mode magnetic inertial fusion to the millijoule level by applying dual-wavelength laser irradiation to the central plate of a cryogenic deuterium target, which is typically a cubic target. In the center of the cubic target located in a biased magnetic field, there is a nanometer hole for generating a new magnetic field. The target also contains lithium nanoparticles that enhance energy deposition and produce tritium through lithium-neutron reactions, further improving the overall efficiency of the fusion process.