76 results about "Fusion power" patented technology

The invention discloses a low-temperature pump for a fusion device and the fusion device, and relates to the field of fusion devices.The low-temperature pump comprises a low-temperature pump body, an adsorption space is defined by the low-temperature pump body, and a first medium inlet communicating with the adsorption space is formed in the low-temperature pump body; the valve assembly is arranged on the cryogenic pump main body, and the valve assembly is used for opening or closing the first medium inlet; and at least part of the adsorption assembly is arranged in the adsorption space, the adsorption assembly is used for adsorbing gas in the adsorption space, and the adsorption assembly is detachably arranged on the cryogenic pump body. Therefore, the adsorption assembly is detachably arranged on the cryopump main body, the adsorption assembly can be independently replaced, the maintenance cost of the cryopump can be reduced, the production cost of fusion energy can be reduced, the economic benefit is further improved, and the adsorption assembly can be replaced without shutdown under the condition that a certain adsorption assembly is replaced.

Development of technologies for effectively suppressing edge localized modes (ELM), maintaining core plasma stability, controlling plasma rotation, adjusting edge transport barriers, achieving smooth transitions between different plasma regimes, minimizing error magnetic fields, sustaining plasma for long periods, stabilizing fusion power, controlling plasma impurities, and optimizing plasma-wall interactions simultaneously in tokamak fusion reactors. [Solution] We provide an adaptive edge-localized 3D magnetic field control system that organically links a real-time plasma state monitoring system, a 3D magnetic field response prediction model, a flexible 3D coil system, an adaptive control algorithm, a plasma regime transition management system, an integrated control interface, a high-precision magnetic diagnostic system, a fusion power control system, a plasma impurity control system, and a plasma-wall interaction optimization system.

The invention relates to a fusion power supply harmonic suppression method based on an energy storage type STATCOM. The method comprises the following steps: determining a harmonic amplification factor K value; selecting and designing a proper discrete digital band-pass filter, and detecting a target frequency band and filtering characteristic sub-harmonics; the detected harmonic voltage amplitude and phase are used as references, an energy storage type STATCOM is adopted to output same-frequency and same-phase harmonic current, virtual damping is formed at a grid-connected point, a K value is used as a damping coefficient, the output harmonic current reference amplitude is determined, virtual harmonic damping is controlled, and harmonic resonance is suppressed. The virtual harmonic damping method for the energy storage type STATCOM is provided for accurate tracking of low-frequency harmonic and inter-harmonic voltage amplitudes and phases, the chain type STATCOM has the advantages of being high in high-voltage direct-hanging efficiency, high in redundancy fault-tolerant capability and the like and is suitable for high-voltage large-capacity scenes, virtual damping control achieves harmonic suppression by adjusting virtual damping at the harmonic frequency of a control structure, and the energy storage type STATCOM can be applied to high-voltage large-capacity scenes. And the system stability can be effectively improved while harmonic waves are treated.

The invention discloses a fusion power generation system, a power generation control method, a storage medium and a controller, and relates to the technical field of fusion energy. The fusion power generation system comprises a steam generator set, a plurality of Tokamak devices and a plurality of thermal conversion units, the Tokamak devices and the thermal conversion units are in one-to-one correspondence, each thermal conversion unit is provided with a first channel and a second channel, and the Tokamak devices and the first channels of the corresponding thermal conversion units form a cladding cooling loop. The steam generator set and a plurality of second channels connected in sequence form a power generation loop; wherein the plurality of Tokamak devices are configured to operate in an alternating or complementary manner; the thermal conversion units are configured to receive heat from the corresponding cladding cooling loops and convert working media in the power generation loops into steam through the heat so as to drive the steam generator set to generate power. According to the system, the plurality of Tokamak devices operate in an alternating or complementary mode, so that heat loss can be reduced, the power generation efficiency is improved, and the plasma control difficulty is reduced.

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 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 provides a laser fusion pellet and a fusion power generation and propulsion system, and the laser fusion pellet is spherical and sequentially comprises a deuterium-tritium gas layer, a solid fusion material layer, a deuterium-helium fuel layer and a high-density carbon spherical shell layer from inside to outside; the fusion power generation and propulsion method provided by the invention comprises the following steps of: driving implosion of the spherical pellet by adopting multiple beams of large-energy repetition-frequency laser, igniting deuterium and helium fuel with higher ignition threshold temperature by utilizing deuterium and tritium fuel with lower ignition threshold temperature, and generating and propelling the magnetic fluid through fusion energy released by pulse type fusion through the magnetic fluid power generation and propulsion device. The power is converted into electric energy or space propulsion power which is stably output; the device has the characteristics that fusion energy release with high repetition frequency and high laser energy utilization efficiency can be realized in a normal temperature state, and the device is not only suitable for fusion power generation on the earth, but also suitable for fusion power generation of extraterrestrial celestial bodies with rich helium fuel such as the moon and space propulsion of spacecrafts.

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 relates to the technical field of fusion energy heat feedback systems, in particular to a loop structure of a fusion energy heat feedback system. According to the technical scheme, the device comprises a cladding cooling loop and a divertor cooling loop; the cladding cooling loop comprises a cladding, a main circulating pump I, a steam generator, a heater and a voltage stabilizer I which are connected in sequence to form a loop; the first main circulating pump is connected with a first baking small-flow pump in parallel, the steam generator is connected with a first flow adjusting valve and a first baking cooler in parallel, and the heater is connected with a second flow adjusting valve in parallel. The divertor cooling loop comprises a divertor, a second main circulating pump, a main heat exchanger, a second baking small-flow pump and a second voltage stabilizer which are sequentially connected to form the loop. The problem of high-temperature baking of internal parts of the fusion reactor is effectively solved, fusion energy is safely, stably and efficiently output for power generation, energy shortage and environmental pollution are relieved, the practical process of nuclear fusion energy is accelerated, and the system has multiple safety guarantee mechanisms.

The invention discloses a cooperative control method for improving Tokamak radio frequency wave current driving locality, and the method mainly comprises the following steps: S1, according to a radial position where locality needs to be enhanced, heating narrow resonance layer electrons at the corresponding radial position through electron cyclotron resonance heating (ECRH); s2, ion cyclotron resonance heating (ICRH) is adjusted for regional heating, so that the radial position of an ICRH driving current main peak value coincides with the radial position of an ECRH current peak value; s3, using GENRAY and CQL3D programs to simulate low hybrid wave (LHW) and high harmonic fast wave (HHFW) combined current driving, calculating a momentum region corresponding to a synergistic effect in a momentum space, performing correlation analysis on the synergistic momentum region, wave emission parameters and current radial distribution, feeding back the parameter adjustment direction, and performing repeated iteration until required local current distribution is achieved; according to the invention, current driving with consideration of driving efficiency and locality control is realized, and the method is of great significance in enhancing the current distribution control capability, improving the constraint performance of plasma and obtaining longer constraint time and higher fusion power.

The invention is a fusion reactor and can solve energy problems. The reactor could be particularly important for the automotive industry because it can be used as a primary energy source. It enables the advancement of electromobility and could be installed in any vehicle. The reactor consists of a fusion chamber containing two fluid accelerators designed to send a fusion-capable, incompressible liquid in the form of very small microdroplets, generated in pairs, to a collision point. The microdroplets are then forced into collision at speeds of approximately 50–200 km / s. Due to the very high speed of the microdroplets, partial nuclear fusion occurs at the collision point, releasing energy that accelerates the components of the microdroplet in all directions and also impacts the following microdroplets, leading to additional nuclear fusion reactions there.The molecules / atoms of the liquid are additionally optimally aligned by electric fields for nuclear fusion of the deuterium atoms, directly at the collision point.

The present disclosure relates to a power cycle system incorporated into a fusion power plant and which may adapt to the operational needs of the plant and reactor therein. The power cycle system comprises means for carrying a working fluid, indirect heating means configured to indirectly heating the working fluid using heat from a reactor of the fusion power plant, direct heating means configured to directly heat the working fluid, and a turbine configured to generate electrical power using heated working fluid. The system comprises a first mode of operation in which working fluid is indirectly heated using the indirect heating means while the direct heating means is thermally decoupled from the working fluid, and a second mode of operation in which the working fluid is heated using the direct heating means while the indirect heating means is substantially thermally decoupled from the working fluid.

The invention discloses a primary and secondary fusion built-in isolation knife circuit breaker, and relates to the field of primary and secondary fusion power distribution equipment for a power distribution network, the primary and secondary fusion built-in isolation knife circuit breaker comprises a pole-mounted circuit breaker and a mechanism box, the body of the pole-mounted circuit breaker is integrated with three current transformers, and the mechanism box is fixedly connected to one side of the pole-mounted circuit breaker; three electrical interface holes used for containing current transformers are formed in the box wall of the mechanism box, an isolation disconnecting link unit is arranged in the mechanism box, the isolation disconnecting link unit is internally arranged and integrated in the mechanism box, the isolation disconnecting link unit and a pole-mounted circuit breaker form an integrated design, the overall structural layout is greatly simplified, the structure is simple, and the cost is low. And the three current transformers integrated on the pole-mounted circuit breaker body are directly butted with the moving contact mechanism through the electrical interface holes preset in the mechanism box, so that the connection is convenient, the contact between the electrical connection part and the external environment is reduced, the erosion of environmental factors such as outdoor wind and rain, dust, corrosive gas and the like is effectively isolated, and the operation stability is ensured.

A controlled fusion process is provided that can produce a sustained series of fusion reactions: a process that (i) uses a substantially higher reactant density of the deuterium and tritium gases by converging cationic reactants into the higher reaction density at a target cathode rather than relying on random collisions, the converging producing a substantially higher rate of fusion and energy production; (ii) uses a substantially lower input of energy to initiate the fusion; (iii) can be cycled at a substantially higher cycle frequency; (iv) has a practical heat exchange method; (v) is substantially less costly to manufacture, operate, and maintain; and, (vi) has a substantially improved reaction efficiency as a result of not mixing reactants with products.

Power management systems for fusion energy devices are provided. Scalable and modular systems which enable a fusion energy device to be powered by conventional power grids are provided through an array of energy storage units configured to exhibit a suitable discharge rate, an array of DC / DC modules coupled to the array of energy storage units, and an array of fast discharge units coupled to the array of DC / DC modules.

The article forms part of a device for producing nuclear fusion energy.

The application discloses a fusion power generation system, a power generation control method, a storage medium and a controller, and relates to the technical field of fusion energy. The fusion power generation system comprises a steam generator unit, a plurality of tokamak devices corresponding to the steam generator unit in one-to-one correspondence and a plurality of heat conversion units, the heat conversion unit is provided with a first channel and a second channel, the tokamak device and the first channel of the corresponding heat conversion unit form a blanket cooling loop, and the steam generator unit and a plurality of sequentially connected second channels form a power generation loop; wherein the plurality of tokamak devices are configured to operate in an alternating or complementary manner; the heat conversion unit is configured to receive heat from the corresponding blanket cooling loop, and convert the working medium in the power generation loop into steam by using the heat to drive the steam generator unit to generate power. The system can reduce heat loss, improve power generation efficiency and reduce the difficulty of plasma control by operating the plurality of tokamak devices in an alternating or complementary manner.

The invention relates to the technical field of nuclear fusion power generation, in particular to a fusion power plant system based on multiple reactors, one machine and a horizontal steam generator. The following technical scheme is provided mainly for solving the problems that a one-reactor one-machine matching mode adopted by an existing fusion power plant cannot adapt to a large-capacity and high-parameter steam turbine set, the system is complex and high in cost due to the fact that an additional energy storage system is depended on, and economical and stable power generation is difficult to achieve. Comprising a double-pile energy supply unit, a single-unit power generation unit, a loop driving unit and an alternate switching control unit, and the double-pile energy supply unit and the single-unit power generation unit form a switchable energy supply and power generation loop through the alternate switching control unit and the loop driving unit. Through the design of multi-reactor one-machine matching and multi-reactor alternate operation, a high-capacity unit can be adapted without additional energy storage, the problems that an existing scheme is low in efficiency, high in cost and complex in system are solved, and the economical efficiency and reliability of a fusion power plant are remarkably improved.

The invention relates to the field of assembly of fusion energy experimental device parts, and discloses an assembly device for a flexible gravity supporting device. The two assembling mechanisms are fixed to the supporting platform, each assembling mechanism comprises a lateral limiting part and a lower limiting part, a limiting groove is formed in each lower limiting part, and each lower limiting part is provided with a plurality of fixing structures; the assembling mechanism further comprises an upper limiting part, and the upper limiting part is used for being fixedly assembled with the base plate and then assembled with the corresponding flexible plate in a matched mode so that the spacing distance between the outer side edge of the base plate and the outer side edge of the adjacent flexible plate can be the target distance. The assembling mechanism further comprises a clamping part, the clamping part comprises a fixing rod and a plurality of clamping blocks, and the clamping blocks are suitable for being connected with the adjacent flexible plates, facing the side of the lateral limiting part, of the corresponding base plate in an abutting mode so that the corresponding flexible plates can be clamped. The flexible gravity supporting device is assembled through the assembling device, assembling is easy, the assembling precision can be improved, and the assembling efficiency of the gravity supporting device can be improved.

This invention discloses a cryogenic pump for a fusion device and a fusion device. The cryogenic pump, relating to the field of fusion devices, includes: a cryogenic pump body defining an adsorption space, and a first medium inlet communicating with the adsorption space; a valve assembly disposed on the cryogenic pump body for opening or closing the first medium inlet; and at least one adsorption component, at least a portion of which is disposed within the adsorption space for adsorbing gas within the adsorption space, and which is detachably disposed on the cryogenic pump body. Therefore, by detachably disposing of the adsorption component on the cryogenic pump body, the adsorption component can be replaced individually, which helps reduce the maintenance cost of the cryogenic pump, thereby reducing the production cost of fusion energy and improving economic efficiency. Furthermore, when replacing a single adsorption component, the entire adsorption process can be continuously replaced.

The invention relates to the technical field of fusion energy, in particular to a method and a system for measuring fusion energy and fusion power and a measuring system.The measuring system comprises a vacuum pipeline, a vacuum pump set, a gas cylinder, an analysis bottle and a pressure gauge, and the gas inlet end of the vacuum pump set is communicated with a fusion device through the vacuum pipeline; the gas cylinder is communicated with the gas outlet end of the vacuum pump set through the vacuum pipeline, the analysis bottle is communicated with the gas cylinder, and the pressure measuring end of the pressure meter is communicated with the interior of the gas cylinder; the gas generated by the fusion device is extracted and collected, helium in the gas is separated through an analysis bottle by adopting a chemical reaction method or a cooling method, the proportion of the helium in the gas is determined, and finally the fusion energy and the fusion power of the fusion device are calculated by combining the pressure, the temperature and the gas composition proportion of the gas bottle.

A breeder blanket is disposed within a stellarator. The breeder blanket defines a breeder zone through which a particle and a flow gas flows. The particle interacts with a neutron generated by a fusion reaction within the stellarator to generate heat. The flow gas absorbs the heat. A separator at an outlet of the breeder blanket separates the flow gas from the particle. The heat in the flow gas is used to generate power.

This invention belongs to the field of power control technology and discloses a method and system for uninterrupted power supply control of the main core of a dual-core fusion power supply. The method includes: collecting historical power consumption data and equipment operating cycle data from the load, and combining this with real-time operating status data to extract the predicted peak power, peak arrival time, and cumulative energy demand; acquiring the real-time state of charge and rated capacity of the sub-core, calculating the expected power supply duration based on the cumulative energy demand, and generating a feedforward power supply trigger signal; pre-starting the main core to preheat to standby mode and pre-setting the ready states of each switch, and determining the target output power and power ramp-up rate of the main core; when the real-time state of charge of the sub-core drops to a preset homing charge threshold, controlling the main core based on the target output power and power ramp-up rate. This invention can effectively improve the power supply continuity, voltage stability, and system safety of a dual-core fusion power supply under complex load conditions.

The invention provides a fusion power supply equipment cooling channel water resistance intelligent test system and method, and relates to the technical field of magnet power supply equipment cooling and fluid testing, and the system comprises a test loop communicated with tested equipment. The flow sensor is used for collecting flow and temperature of a medium in a test loop and pressure difference between two ends of tested equipment; the control and data processing module is provided with a temperature control unit which is coupled in a quick connection mode; carrying out cross-temperature zone temperature regulation on the medium; the control and data processing module is configured to receive the data acquired by the acquisition module and perform temperature compensation based on medium density and viscosity on the pressure difference according to the temperature of the medium; calculating the equivalent flow velocity at the measured equipment; and on the basis of the data subjected to temperature compensation and diameter-variable normalization processing according to the equivalent flow velocity, generating a differential pressure-flow relation curve family of the cross-temperature zone. And an accurate, efficient and traceable data basis is provided for design and acceptance inspection of cooling loops of equipment such as a fusion power supply.

The invention discloses an electromagnetic disturbance field circuit hybrid modeling method and system for a primary and secondary fusion switch, and the method comprises the steps: building a three-dimensional full-wave model of the primary and secondary fusion power distribution switch, setting the positions of an electric / magnetic field probe and a connection port, and obtaining the response characteristics of the port; based on the response characteristics, converting the three-dimensional full-wave model into a black box model of a primary and secondary fusion power distribution switch in a circuit; considering the influence of the lightning stroke position on the radiation electromagnetic disturbance characteristic frequency, and building a distribution parameter circuit model of the transmission line; based on the response characteristics, the black box model is imported into the distributed parameter circuit model for simulation, and voltage and current of a connection port are obtained; and the voltage and the current are fed back to the three-dimensional full-wave model, and electromagnetic disturbance field and circuit hybrid modeling is completed. The problem that simulation time is too long or a calculation result is invalid when a three-dimensional full-wave model or a circuit model is singly used is solved.

The present invention provides a laser fusion cross-scale simulation method, system, and terminal based on relay computing. The method utilizes a radiation fluid program to simulate the nanosecond laser-driven fuel implosion collision process, obtaining the post-collision plasma temperature and density distribution. A particle kinetics program is used to simulate the picosecond laser-driven fast electron generation process, obtaining the fast electron beam distribution in phase space. The obtained post-collision plasma temperature and density distribution, as well as the fast electron beam distribution in phase space, are then input into a hybrid kinetics program to simulate the fast electron beam heating process of the colliding plasma, obtaining the colliding plasma heating results. The radiation fluid program is then used to simulate the fusion combustion process based on the colliding plasma heating results, obtaining the neutron yield and fusion energy gain. The present invention utilizes numerical simulation methods at different physical scales to calculate the corresponding physical processes, and couples these different physical processes for relay computing, achieving cross-scale simulation of laser fusion schemes while ensuring controllable computational accuracy and computational complexity.

The invention is a fusion reactor. It consists of a fusion chamber containing two fluid accelerators. The fluid accelerators are designed to produce a fusion-capable, incompressible liquid in the form of very small microdroplets, which are generated in pairs and collide with each other at a collision point. The microdroplets are sent towards each other at a collision point at approximately 50-100 km / s. Due to the very high speed of the microdroplets, nuclear fusion occurs at the collision point, releasing energy that accelerates the components of the microdroplet in all directions and also impacts the following microdroplets, leading to additional nuclear fusion reactions there. The molecules / atoms of the liquid are additionally aligned by electric fields directly at the collision point, optimally aligning them for nuclear fusion of the deuterium atoms.An electromagnetic coil focuses the structure and shape of the electrically charged micro-droplets more closely together at the meeting point, thus increasing the number of atoms that fuse together.

The present invention discloses a three-sensor measurement method and structure for a super-annular float pull-up magnetic levitation system, relating to the field of magnetic levitation technology. The method solves the problem of range-finding sensors on the same horizontal plane as the float in a dipole magnetic confinement fusion device occupying the low-compression ratio confinement area of ​​the plasma. The present invention establishes a float coordinate system at the float's location, translates the float coordinate system vertically upward to obtain a sensor coordinate system, sets three zero-point references for the light emitted by laser range-finding sensors in the sensor coordinate system, measures the distances between the zero-point references and the corresponding projected points in the float coordinate system, and calculates the attitude angle of the float and the distance between the center of the float's upper surface and the sensor. The present invention uses only three vertical laser range-finding sensors to provide feedback signals for the two attitude angles and one suspension distance required for super-annular float suspension control, eliminating the need for laser range-finding sensors on the horizontal plane and leaving low-compression ratio space for fusion energy absorption components.

An apparatus and method for integrated tritium extraction and recovery in a fusion power system includes combining-in a tritium extraction unit-a fluid tritium breeding composition with a second fluid to generate a combined fluid undergoing two phase flow, and extracting tritium from the breeding composition in the two-phase flow by simultaneous processes of permeation across a solid membrane and tritium transfer onto the second fluid (i.e., gas-liquid or liquid-liquid contacting).

A compact, modular, and scalable pulsed power-driven radiation source system utilizes Dense Plasma Focus assemblies and Ion Ring Marx Generators in a novel configuration to generate ultra-intense charged particle beams. The system's WARP core integrates coaxially aligned, face-to-face Dense Plasma Focus assemblies with reflex triodes and magnetic flux compression to achieve significantly enhanced energy outputs. The invention enables efficient energy production, advanced propulsion capabilities, and new avenues for high-energy physics research while maintaining a reduced physical footprint compared to traditional accelerators. The system achieves GeV-level particle energies through controlled plasma and charged particle ring compression and acceleration, offering applications in nuclear fusion, advanced space propulsion, and radiographic analysis.