185 results about "Nuclear fusion" patented technology

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 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 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 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.

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.

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 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 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.

Arrangement (16) for generating EUV radiation or for operating nuclear fusion by irradiating a target material (18) with a laser beam (14). The arrangement comprises a target chamber (20) which has an interior (22) with a target area (24) for irradiating the target material (18) with the laser beam (14), an insertion device (26) for introducing the target material (18) into the target area (24), and a manipulation device (34) for shaping and / or positioning the target material (18) in the target area (24).

The application provides a multi-heat source combined energy storage and auxiliary heating system and method of a nuclear fusion device, and belongs to the field of nuclear fusion device energy conversion and utilization, and comprises: a high-temperature heat source storage and supply system, which is used for receiving and storing the heat of blanket and breeding zone coolants, and continuously outputs high-temperature heat sources during the operation and suspension of a fusion reactor; a medium-temperature heat source and auxiliary supply system, which is used for receiving the heat of a divertor coolant, and supplements the output of medium-temperature heat sources through a medium-temperature auxiliary heater during the suspension of the fusion reactor; and a low-temperature heat source and auxiliary supply system, which is used for receiving the heat of a vacuum chamber coolant, and supplements the output of low-temperature heat sources through a low-temperature auxiliary heater during the suspension of the fusion reactor; and 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 are independently operated. The application continuously and stably provides high-temperature heat, medium-temperature heat and low-temperature heat to the outside during the operation and suspension of the fusion reactor.

The present invention refers to a type of reactor for initiating and carrying out a nuclear fusion reaction, use of plasmonic material in initiating a nuclear fusion reaction, and a method for initiating a nuclear fusion reaction. By using a plasmonic material to affect resonance effect, preferably plasmonic enhancement effect, a Coulomb explosion can be triggered, and in turn a nuclear fusion reaction can be initiated.

The present invention relates to a remotely operated system (200) to deploy and recover materials (25) into and from a nuclear fusion device (100), for the purpose of exposing said materials (25) to neutron radiation, which will cause the generation of radioactive isotopes, comprising at least one loop made of pipes (14) with constant inner diameter, a plurality of capsules (23) with an outer diameter slightly smaller than the inner diameter of the at least one loop (14), wherein the capsules (23) are adapted to contain the material (25) to be irradiated by the neutron radiation, a propulsion system for circulating the capsules (23) through the at least one loop (14), a remotely operated capsule filling system (18) for filling said capsules (23) into the at least one loop (14), and a remotely operated capsule recovery system (19) for recovering said capsules (23) from the at least one loop (14).

A plasma nuclear fusion reactor comprises a reactor, a plasma channel is arranged in the reactor, an inlet of the plasma channel is communicated with an outlet of an electromagnetic acceleration channel of a plasma electromagnetic acceleration device, the inner end of the plasma channel is communicated with a plasma nuclear fusion chamber, and the inner wall of the plasma nuclear fusion chamber is an arc-shaped surface; the plasma electromagnetic acceleration device comprises a machine shell, a positive excitation conductor and a negative excitation conductor are arranged in the machine shell in parallel, the positive excitation conductor is connected with a positive pole of an excitation power supply, the negative excitation conductor is connected with a negative pole of the excitation power supply, and an electromagnetic acceleration channel capable of being vacuumized is arranged between the positive excitation conductor and the negative excitation conductor. The invention aims to provide the plasma nuclear fusion reactor which can rapidly accelerate plasmas, enables the plasmas to move at a high speed and have huge kinetic energy, and further enables the plasmas to enter the plasma nuclear fusion chamber and generate a nuclear fusion reaction.

This invention relates to the field of nuclear fusion reactor materials technology, specifically to a low-activation ferritic / martensitic steel CLF-1 for nuclear fusion reactor blankets, its preparation method, and its applications. The steel's chemical composition, by mass percentage, is: Cr: 8.0-9.0%, W: 1.4-1.6%, V: 0.2-0.3%, Ta: 0.06-0.1%, Mn: 0.3-0.5%, C: 0.07-0.12%, Gd: 0.03-0.06%, N≤0.02%, with the balance being Fe and unavoidable impurities of a specific content. The microstructure is tempered lath martensite, possessing excellent room-temperature and high-temperature mechanical properties, thermal properties, and radiation resistance. This steel is effectively adapted to the extreme working environment of nuclear fusion reactor blankets and is suitable for manufacturing structural components for nuclear fusion reactor blankets.

A magnetic field confinement type nuclear fusion device (1) includes a first member (e.g., a cladding (20)) containing a non-magnetic austenitic steel. The nonmagnetic austenitic steel contains 28% by mass or more and 31% by mass or less of Mn, 5% by mass or more and 7% by mass or less of Al, 0.5% by mass or more and 2% by mass or less of Si, 0% by mass or more and 0.3% by mass or less of C, 0% by mass or more and 1.5% by mass or less of Y2O3, and the balance Fe and unavoidable impurities.

The application discloses a sustained combustion type plasma nuclear fusion chamber. The chamber comprises a shell, a plasma channel is arranged in the shell, the plasma channel is a tapered pipeline from an inlet end to an outlet end, the inlet of the plasma channel is communicated with the outlet of an electromagnetic acceleration channel of a plasma electromagnetic acceleration device, the inner end of the plasma channel is communicated with a plasma nuclear fusion cavity, the inner wall of the plasma nuclear fusion cavity is an arc surface, a nuclear fusion sustained combustion cavity is arranged on the inner wall of the plasma nuclear fusion cavity, and the nuclear fusion sustained combustion cavity is filled with nuclear fusion fuel. The sustained combustion type plasma nuclear fusion chamber can make plasma enter the plasma nuclear fusion chamber and generate primary nuclear fusion, and the primary nuclear fusion can transmit heat to the nuclear fusion fuel in the nuclear fusion sustained combustion cavity, thereby triggering secondary nuclear fusion.

The invention provides a linear nuclear fusion device and an application method. The linear nuclear fusion device comprises a non-metal vacuum chamber, a coil assembly, a power supply system and a control system. By adopting an FRC configuration without a central conductor, a core large-scale component of a traditional fusion device is omitted; the high space utilization rate and the high integration of functional areas are realized through linear, centrosymmetric and five-section layout; the conical acceleration area has acceleration and compression functions, so that independent modules are reduced, and the compactness of the device is improved; the high consistency of two groups of FRC plasmas in quality, speed and phase is ensured through linear, centrosymmetric and five-section layout, and the reliability of the device is remarkably improved; in addition, the non-metal vacuum chamber is adopted, and the non-metal vacuum chamber can be made of non-metal materials such as quartz or ceramic, so that eddy-current loss and impurity sputtering of a metal wall surface in a pulsed magnetic field are avoided, the service life of FRC plasmas is prolonged, and the fusion reaction efficiency is improved.

The present application relates to the technical field of nuclear fusion, and discloses a method and a device for measuring discharge current in a nuclear fusion device, the method being applied to the device for measuring discharge current in the nuclear fusion device, and the device comprising a mutual inductance type current acquisition module and a shunt; the method comprises: obtaining first current data collected by the mutual inductance type current acquisition module between a discharge starting moment of a power supply in the nuclear fusion device and a preset moment; obtaining second current data collected by the shunt between the preset moment and a discharge ending moment of the power supply; and splicing the first current data and the second current data according to the acquisition time sequence to obtain discharge current data; the above embodiment can effectively avoid the appearance of a step signal, more accurately measure an actual current signal, and ensure the current acquisition accuracy in the entire current signal acquisition process.

The application discloses a method and device for preparing elements on demand by means of controllable nuclear fusion-nuclear transmutation with deuterium (hydrogen isotope) as the only raw material, belonging to the technical field of controllable nuclear physics and element synthesis, and suitable for laboratory small-batch research scenarios. The core is that under controllable conditions in the laboratory, 10-15 MeV high-energy neutrons are generated by deuterium nuclear fusion, and low-radioactivity / stable target materials are directionally bombarded, and stable products such as noble metals and rare earth elements are directionally prepared through nuclear transmutation and decay (1-50g per single preparation), the reaction by-products can be recycled, the fusion energy recovery rate is greater than or equal to 30%, and the external power supply accounts for less than or equal to 70%, which does not constitute unlimited energy output. The total floor area of the device is less than or equal to 10 m2, and the total power is less than or equal to 200 kW, and the device has the advantages of wide raw material sources, environmental friendliness, strong controllability and the like, and can be applied to the fields of noble metal preparation, new energy material synthesis, harmless treatment simulation of nuclear waste and the like, and fills the technical gap of global laboratory-level deuterium-based element preparation on demand.

The invention discloses an ultra-low temperature vacuum system of a Tokamak or star imitator adaptive to nuclear fusion, and relates to the technical field of nuclear fusion equipment, the ultra-low temperature vacuum system comprises a vacuum chamber, a plasma state sensor is embedded in the inner wall of the vacuum chamber, the outer end of the vacuum chamber is provided with a sealing interface, the outer end of the sealing interface is provided with a primary filter, and the primary filter is provided with a secondary filter. A getter bin is installed at the outer end of the primary filter, an auxiliary pump is installed at the outer end of the getter bin, a stop valve is installed at the outer end of the auxiliary pump, a cold trap is installed at the outer end of the stop valve, the side wall of the cold trap is connected with a refrigerating machine through a pipeline, and a main pump is installed at the outer end of the cold trap. By arranging a series of structures, the pain point of decoupling of a traditional system and plasma operation is thoroughly solved, all the components cooperate to guarantee the ultrahigh vacuum environment, interference of impurity gas on plasma constraint is greatly reduced, and the stability and success rate of a nuclear fusion experiment are remarkably improved.

A nuclear fusion device and a method for controlling nuclear fusion intensity are disclosed. The nuclear fusion device includes a nuclear beam generation unit that emits a nuclear beam, a reaction vessel filled with nuclear fusion material, a thermal energy output system and an electrical energy output system that convert the energy produced by the nuclear fusion reaction into thermal energy and electrical energy for output. The reaction vessel receives the nuclear beam, which reacts with the nuclear fusion material inside to produce neutrons, achieving a neutron nuclear fusion cycle reaction and releasing energy. The nuclear beam includes at least one of a triton beam with a single nucleus energy of 50 KeV-1 MeV, a deuteron beam with a single nucleus energy of 100 KeV-5 MeV, and a proton beam with a single nucleus energy of 2-10 MeV; the nuclear fusion material includes polyatomic molecules, which at least include 6LiD and 7LiD.

A manufacturing method of a large-scale integrated laser ignition nuclear fusion device is characterized in that a recording machine technology is used for manufacturing equipment capable of rapidly punching holes with different angles in a large scale, the equipment is used for punching a large number of holes capable of pointing photon beams emitted by placed lasers to the same point, and the number of the holes is determined according to ignition nuclear fusion reaction requirements; the hole diameter is determined by equipment precision and ignition nuclear fusion needs.

The invention relates to the technical field of nuclear fusion experiment data processing and numerical simulation, and discloses an automatic concurrent physical analysis method and system for a magnetic confinement fusion device, and the method comprises the steps: S1, receiving input parameters including a shot number list and a time slice list, and constructing a directed acyclic graph; s2, scheduling and executing based on the directed acyclic graph: S2.1, requesting diagnosis and balancing original diagnosis data from a plurality of data source interfaces in parallel; s2.2, converting the coordinate system of the obtained original diagnostic data into a unified normalized small-radius magnetic flux surface coordinate, and performing profile fitting to obtain profile data; s2.3, executing multi-physical coupling calculation with a dependency relationship to generate convergent plasma balance and profile information; s3, verifying the data in the process and performing grading processing on exceptions; s4, writing the final result and the intermediate result into an HDF5 file; and S5, recording full-link metadata and a running log from data acquisition to result output. According to the invention, one-button analysis is realized, and the analysis efficiency is improved.

The application discloses a kind of particle evolution simulation methods based on multi-component plasma radiation effect in tokamak, belong to magnetic confinement controlled nuclear fusion technical field.Firstly, the evolution of impurity density distribution, electron density distribution and ion density distribution is calculated, then continuous radiation and linear radiation are calculated, and then a variety of plasma radiation is accurately added inside magnetic island.Calculating the magnetic field configuration under the plasma radiation correction, and continue to calculate the evolution of plasma total radiation and related parameters under advanced magnetic field configuration, so repeated calculation, achieve the simulation effect of long time evolution.The application realizes the calculation of impurity, electron and ion real-time dynamic distribution, and can also calculate the evolution of a variety of plasma radiation under real three-dimensional magnetic field configuration, and then obtain the plasma related parameter profile at any time;Meanwhile, the spatial distribution of plasma radiation and the situation of magnetohydrodynamic instability under advanced magnetic field configuration are more accurately described.

The present application provides a system and method for measuring cesium evaporation rate in a fusion device offline, comprising a vacuum chamber, a cesium crucible assembly, a heating assembly, a film thickness gauge, a laser absorption spectroscopy system and a vacuum pumping unit. The present application uses the vacuum pumping unit to provide an ultra-high vacuum environment for the whole device including the vacuum chamber; then uses the heating assembly to heat the cesium crucible and the transmission pipeline to ensure the effective evaporation of cesium and reduce the deposition of cesium on the pipeline wall; then uses the film thickness gauge and the laser absorption spectroscopy system to measure the deposition thickness of cesium and the concentration of cesium atoms, and cross-check the measurement results of the two diagnostic methods; realize the measurement of cesium evaporation rate and obtain the quantitative relationship between the cesium evaporation rate and the heating temperature; finally transplant the measurement system to the negative ion source to realize the real-time monitoring of the cesium injection amount in the vacuum stage. The present application provides effective data and technical support for cesium flow control in the magnetic confinement nuclear fusion negative neutral beam injection system.