55 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 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 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 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.

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 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.

The present invention relates to the technical field of fusion energy heat feed systems, and in particular to a loop structure of a fusion energy heat feed system. Its technical solution includes a blanket cooling loop and a divertor cooling loop; the blanket cooling loop includes a blanket, a main circulation pump 1, a steam generator, a heater, and a pressurizer 1 connected in sequence to form a loop; the main circulation pump 1 is connected in parallel with a baking low-flow pump 1, the steam generator is connected in parallel with a flow regulating valve 1 and a baking cooler 1, and the heater is connected in parallel with a flow regulating valve 2; the divertor cooling loop includes a divertor, a main circulation pump 2, a main heat exchanger, a baking low-flow pump 2, and a pressurizer 2 connected in sequence to form a loop. The present invention effectively solves the problem of high-temperature baking of internal components of a fusion reactor, realizes the safe, stable, and efficient output of fusion energy for power generation, alleviates energy shortages and environmental pollution, accelerates the practical application of nuclear fusion energy, and the system has multiple safety assurance mechanisms.

This invention relates to the field of steel structure anti-corrosion coating monitoring technology, and particularly to a multi-sensor fusion-based online monitoring method and system for quantitative early warning of anti-corrosion coatings on power grid steel structures. The method includes: deploying sensor components in the monitored area of ​​the power grid steel structure and collecting monitoring data, including coating electrochemical parameters, substrate corrosion parameters, environmental parameters, and electromagnetic field parameters; determining the coating degradation degree based on the coating electrochemical parameters and substrate corrosion parameters; determining an environmental corrosion correction coefficient based on the environmental parameters; determining an electromagnetic field influence coefficient based on the electromagnetic field parameters; and generating a coating health status assessment result based on the coating degradation degree, environmental corrosion correction coefficient, and electromagnetic field influence coefficient. The coating health status assessment result generated by this invention can reflect the degradation state of the anti-corrosion coating itself and clarify the degree of influence of the power grid electromagnetic field on the coating degradation process, thus providing information dimensions that better meet the needs of power grid steel structure anti-corrosion operation and maintenance.

The utility model relates to a reactor system, a laser generation system and a fusion reactor system for space application. The reactor system comprises a reactor, at least one satellite system, an optical cavity, an optical path modifying device, at least one pair of reflecting mirror devices, a timing device and a space driving device. The present disclosure provides a fusion energy system configured with a high intensity pulsed laser system in a compact and spatially efficient system; the high-intensity pulse laser system provides enough energy to ignite and maintain fusion energy configured in space application; the present disclosure provides the advantage of using this high intensity laser in space to produce fusion energy through efficient size, weight and cost.

A fuel target device for an inertial confinement fusion process. The device comprises a center region is comprising a first fuel layer of deuterium-tritium-lithium ((DT)(1-x)Lix, 0<x<0.5) fuel characterized by a higher or equal ignition temperature in comparison with a lowest ignition temperature of deuterium-tritium (DT). The device comprises a second fuel layer of deuterium-tritium (DT) fuel characterized by the lowest ignition temperature is surrounding the center region, and a third fuel layer comprising an outer region of a pure hydrogen (H2) or a proton rich boron (pyB(1-y)11, 1>y>0.5) material is surrounding the deuterium-tritium (DT) fuel such that the deuterium-tritium (DT) fuel is sandwiched between the deuterium-tritium-lithium ((DT)(1-x)Lix, 0<x<0.5) fuel and the pure hydrogen or proton rich boron (pyB(1-y)11, 1>y>0.5) material.

The invention discloses a multi-energy fusion power generation scheduling method and system based on power gap prediction. The method comprises the steps that a power gap curve in a future preset time period is calculated based on collected environmental meteorological data and historical load data; extracting a power gap amplitude and a corresponding gap duration based on the power gap curve; the gap duration is compared with a preset time threshold value, a comparison result is obtained, and the time threshold value is used for defining the time limit of the short-time power gap; and according to a comparison result, determining a target response main body matched with the gap duration, and generating a dynamic operation strategy based on the target response main body. Compared with the prior art, the power gap prediction precision, the matching degree of the response strategy and the gap duration and the equipment operation economy of the multi-energy system can be remarkably improved, and the technical defects that in a traditional scheme, power gap prediction deviation is large, the response strategy and the gap duration are not matched, and equipment is frequently started and stopped, and losses are high are overcome.

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 invention firstly provides a fusion power supply of a railway vehicle and the railway vehicle, the railway vehicle comprises a waste discharge device, the fusion power supply is arranged in the waste discharge device, and a waste discharge fan of the waste discharge device is used for heat dissipation. The invention further provides a railway vehicle. According to the fusion power supply of the railway vehicle and the railway vehicle, the fusion power supply and the waste discharge device are integrated, the waste discharge fan of the waste discharge device is used for cooling the fusion power supply, a cooling device does not need to be independently arranged for the fusion power supply, and the space of the waste discharge device can be fully utilized; the available space of the vehicle is improved.

This invention discloses a passive buffer circuit for fusion power supplies and a fusion power supply, belonging to the field of power electronics technology. The passive buffer circuit includes: a coupling inductor L. k Buffer resistor R, capacitor C, diode D s and capacitor C s The capacitor C and the coupling inductor L k The primary side and the buffer resistor R are connected in series and then in parallel to the source and drain of the fusion power supply's IGBT. The capacitor C s Parallel to the coupled inductor L k The diode D at both ends of the secondary side s The positive and negative terminals are respectively connected to the coupled inductor L k The non-identical terminals on the secondary and primary sides. This invention introduces an LC resonant network into the traditional RCD structure to reconstruct the energy dissipation path, effectively reducing peak power and temperature rise, improving heat distribution, and maintaining the high reliability of the passive structure. It is a passive optimization scheme with a simple structure that requires no additional control.