Patents
Literature
36 results about "Neutral beam injection" patented technology
Efficacy Topic
Property
Owner
Technical Advancement
Application Domain
Technology Topic
Technology Field Word
Patent Country/Region
Patent Type
Patent Status
Application Year
Inventor
Neutral beam injection (NBI) is one method used to heat plasma inside a fusion device consisting in a beam of high-energy neutral particles that can enter the magnetic confinement field. When these neutral particles are ionized by collision with the plasma particles, they are kept in the plasma by the confining magnetic field, and can transfer most of their energy by further collisions with the plasma. By tangential injection in the torus, neutral beams also provide momentum to the plasma and current drive, one essential feature for long pulses of burning plasmas. Neutral beam injection is a flexible and reliable technique, which has been the main heating system on a large variety of fusion devices. To date, all NBI systems were based on positive precursor ion beams. In the 90s there has been impressive progress in negative ion sources and accelerators with the construction of multi-megawatt negative ion based NBI systems at LHD (H⁰, 180 keV) and JT-60U (D⁰, 500 keV). The NBI designed for ITER is a substantial challenge (D⁰, 1MeV, 40A) and a prototype is being constructed to optimize its performance in view of the ITER future operations. Other ways to heat plasma for nuclear fusion include RF heating, electron cyclotron resonance heating (ECRH), and ion cyclotron resonance heating (ICRH), Lower hybrid resonance heating (LH).
System and method for off-line measurement of cesium evaporation rate in fusion device
ActiveCN119643480APromote productionincrease coverageNuclear energy generationColor/spectral properties measurementsEvaporation (deposition)Ultra-high vacuum
The invention provides a system and a method for off-line measurement of a cesium evaporation rate in a fusion device. The system comprises a vacuum chamber, a cesium crucible assembly, a heating assembly, a film thickness meter, a laser absorption spectrum system and a vacuum pumping unit. According to the invention, an ultrahigh vacuum environment is provided for the whole device including the vacuum chamber by using the vacuum pumping unit; then the cesium crucible and the conveying pipeline are heated through a heating assembly, so that effective evaporation of cesium is guaranteed, and deposition of cesium on the wall face of the pipeline is reduced; measuring the deposition thickness of cesium and the concentration of cesium atoms by using a film thickness meter and a laser absorption spectrum system, and checking the measurement results of the two diagnosis methods mutually; the cesium evaporation rate is measured, and the quantitative relation between the cesium evaporation rate and the heating temperature is obtained; and finally, a measurement system is transplanted into a negative ion source, and the cesium injection amount in the vacuum stage is monitored in real time. Effective data and technical support are provided for cesium flow control in the magnetic confinement nuclear fusion negative neutral beam injection system.
Owner:INST OF ENERGY HEFEI COMPREHENSIVE NAT SCI CENT (ANHUI ENERGY LAB)
Compact magnetic deflection system for neutral beam injection
ActiveCN119542099AEffective filteringRemove current heatElectric discharge tubesNuclear energy generationIon beamElectric current flow
The invention discloses a compact magnetic deflection system for neutral beam injection. The compact magnetic deflection system comprises an iron yoke assembly, two magnet assemblies with the same structure and a magnet protection assembly, the iron yoke assembly is of a rectangular frame structure and forms a complete magnetic loop, the two magnet assemblies are oppositely arranged in the iron yoke assembly, and a channel is reserved between the two magnet assemblies. The magnet protection assembly surrounds the two magnet assemblies; the magnet assembly comprises a magnet exciting coil box, an iron core and an electrified coil, two space grooves are formed in the excitation coil box in a rectangular-ambulatory-plane mode, the iron core is located in the space groove in the inner layer, the electrified coil is located in the space groove in the outer layer, and the head end and the tail end of the electrified coil extend out of the side edge of the excitation coil box in the same direction; charged ions flexibly deflect out of an original beam line channel by changing the current of the electrified coil or the number of turns of the coil. According to the invention, mixed charged ion beams can be effectively filtered out, and purified neutral beam injection is realized.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
Neutral beam injection one-shot experiment beam source system ignition analysis method and system
The invention discloses a neutral beam injection one-shot experiment beam source system sparking analysis method and system, relates to the technical field of negative ion source neutral beam injection experiment analysis, and solves the problem that in the prior art, fault tree drawing methods adopted for experiment fault analysis are generally a downlink method and an uplink method, but for a large system, the fault tree drawing method is not suitable for large-scale systems. The two methods have certain limitations, so that the analysis of experimental faults is not thorough; the method comprises the following steps: constructing a fault tree of a target experiment system; analyzing the current fault event based on the fault tree to obtain an upper-layer fault type and a lower-layer fault type corresponding to the current fault event; calculating a priority coefficient of each event in the upper-layer fault type and the lower-layer fault type based on historical experimental data; and processing the current fault event based on the priority coefficient. The technical problem is solved.
Owner:INST OF ENERGY HEFEI COMPREHENSIVE NAT SCI CENT (ANHUI ENERGY LAB)
System and methods for forming and maintaining high energy and temperature FRC plasma via spheromak merging and neutral beam injection
A high performance field reversed configuration (FRC) system includes a central confinement chamber, two divertor chambers coupled to the chamber, and two diametrically opposed spheromak injectors coupled to the divertor chambers. A magnetic system includes quasi-dc coils axially positioned along the FRC system components.
Owner:TAE TECHNOLOGIES INC
Neutral beam injection liquid cooling drift pipeline and controllable fusion equipment
ActiveCN119400457AMeet the length requirementEfficient coolingThermonuclear fusion reactorPlasma technologyNuclear fusion
The invention discloses a neutral beam injection liquid cooling drift pipeline and controllable fusion equipment, and belongs to the technical field of plasma technology and controllable nuclear fusion power generation. The neutral beam injection liquid cooling drift pipeline comprises a drift pipeline assembly and a liquid cooling loop assembly. The drift pipeline assembly comprises an inner shielding layer and an outer shielding layer, and the inner shielding layer is arranged on the inner side of the outer shielding layer; the liquid cooling loop assembly comprises a liquid supply pipeline, a liquid cooling pipeline and a liquid return pipeline, the liquid supply pipeline and the liquid return pipeline are located outside one end of the drifting pipeline assembly, the liquid cooling pipeline is arranged between the inner shielding layer and the outer shielding layer and makes contact with the inner shielding layer and the outer shielding layer, and the input end of the liquid cooling pipeline is connected with the output end of the liquid supply pipeline; and the output end of the liquid cooling pipeline is connected with the input end of the liquid return pipeline. The liquid cooling device can well bear impact of high-energy neutral particles, and is good in shielding effect, easy to manufacture, low in cost and low in liquid cooling medium leakage risk.
Owner:聚变新能(安徽)有限公司 +1
Method for evaluating the effect of plasma toroidal rotation on tokamak hybrid operation
ActiveCN115422752BNuclear energy generationDesign optimisation/simulationPlasma currentParticle physics
The present invention relates to the field of plasma physics technology and discloses a method for evaluating the influence of plasma circumferential rotation on tokamak hybrid operation, comprising: designing the plasma current required for the hybrid operation of the tokamak device based on the parameters of the tokamak device and the auxiliary heating capacity; Ip and vertical field Bt The present invention comprises designing parameters for the neutral beam injection system and the electron cyclotron wave resonance system required for the tokamak's hybrid operation; injecting the initial neutral beam into the tokamak and performing integrated simulation calculations to obtain a first set of operating parameters for the tokamak's hybrid operation; adjusting the torque of the neutral beam injected into the tokamak to calculate a second set of operating parameters for the tokamak's hybrid operation; and analyzing and comparing the first set of operating parameters with the second set of operating parameters. The present invention can independently assess the impact of plasma toroidal rotation on the tokamak's hybrid operation.
Owner:SOUTHWESTERN INST OF PHYSICS
Ion swallowers and neutral beam injection systems
ActiveCN121862487BImprove absorption efficiencyReduce risk of damageRadiation/particle handlingNuclear energy generationParticle physicsNeutral beam injection
This invention relates to the field of nuclear fusion technology, and discloses an ion swallower and a neutral beam injection system. The ion swallower is used for the absorption of high-energy ions and includes: a mounting frame; a first energy absorption target, a second energy absorption target, and a third energy absorption target, all fixed to the mounting frame. The first and third energy absorption targets are opposite to each other and spaced apart along a first direction, and the second energy absorption target is disposed between the first and third energy absorption targets. The first energy absorption target is used to absorb first-energy ions, the second energy absorption target is used to absorb second-energy ions, and the third energy absorption target is used to absorb third-energy ions. By setting the first, second, and third energy absorption targets, the absorption efficiency of the ion swallower for deflected ions is improved, and the risk of ions escaping from the ion swallower into the vacuum chamber and causing damage to other components inside the vacuum chamber is reduced.
Owner:聚变新能(安徽)有限公司 +1
Systems and methods for improved support for high performance frc and high harmonic fast wave electron heating in high performance frc
Systems and methods to facilitate the formation and maintenance of FRCs with excellent stability and particle, energy, and flux confinement, and more particularly, systems and methods to facilitate the formation and maintenance of FRCs with elevated system energy and improved support using neutral beam injection and high-harmonic fast-wave electron heating.
Owner:TRI ALPHA ENERGY INC
A system and method for off-line measurement of cesium evaporation rate in a fusion device
ActiveCN119643480BNuclear energy generationColor/spectral properties measurementsEvaporation (deposition)Ultra-high vacuum
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.
Owner:INST OF ENERGY HEFEI COMPREHENSIVE NAT SCI CENT (ANHUI ENERGY LAB)
Neutral beam power regulation model construction method and device, equipment and medium
PendingCN120724818AData processing applicationsDesign optimisation/simulationData miningNeutral beam injection
The invention discloses a neutral beam power regulation model construction method, apparatus and device, and a medium. The method comprises the steps of obtaining a historical discharge data set of a neutral beam injection experiment; and taking the power and the diversion coefficient in the historical discharge data set as input data, taking the set value of each path of power supply in the historical discharge data set as output data, and inputting the input data and the output data into a pre-constructed deep neural network model for training to obtain a neutral beam power regulation model. According to the scheme, the adjustment model for determining the target power and the setting parameters corresponding to the neutral beam can be provided, energy and time waste in the neutral beam injection process is avoided, and the working efficiency of the Tokamak device is improved.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
Adjusting system and method for realizing steady-state billion-degree ion temperature
The invention discloses an adjusting system and method for realizing steady-state billion-degree ion temperature, and relates to the technical field of magnetic confinement nuclear fusion, and the system comprises a central control unit, and a neutral beam injection unit, a central spiral pipe and an air supply unit of which the output ends are connected with plasma in a vacuum chamber. The neutral beam injection unit is used for heating high-energy neutral atoms emitted by the plasma; the central spiral tube is used for generating and controlling plasma current; the gas supply unit is used for conveying working gas into the vacuum chamber; and the central control unit can respectively adjust the neutral beam injection unit, the central spiral pipe and the air supply unit so as to obtain the required steady-state ion temperature. By adjusting the beam energy and power of the neutral beam injection unit, the plasma electron density and the current climbing rate, the plasma has very high heating power density, ion energy transportation is reduced, heating efficiency is improved, and therefore the steady-state ion temperature of hundred million degrees is obtained.
Owner:SOUTHWESTERN INST OF PHYSICS
Technique for reducing a local thermal load on a surface that is struck by electrically charged particles
PCT designated stageWO2026027060A1Direct voltage acceleratorsNuclear targetsParticle beamParticle physics
The invention relates to a method and a device for reducing a local thermal load on a surface of a particle collection device that is struck by electrically charged particles. The electrically charged particles may correspond in particular to a fraction of non-neutralised ions from a particle beam of neutralised ions downstream of a neutraliser of a neutral beam injection device of a fusion reactor. The method comprises changing, preferably continuously, the point of impact (P) of the charged particles (8) on the surface (34) by exposing the charged particles (8) to at least one magnetic and / or electric field, the field lines of which are oblique or perpendicular to a flight direction of the charged particles and the field strength of which is varied, preferably continuously, in order to change the point of impact (P) so as to reduce a local thermal load on the surface (34), the surface (34) being designed as an area with an open cross-section.
Owner:MAX PLANCK GESELLSCHAFT ZUR FOERDERUNG DER WISSENSCHAFTEN EV
A compact magnetic deflection system for neutral beam injection
This invention discloses a compact magnetic deflection system for neutral beam injection, comprising: a yoke assembly, two identical magnet assemblies, and a magnet protection assembly. The yoke assembly has a rectangular frame structure, forming a complete magnetic circuit. The two magnet assemblies are arranged opposite each other within the yoke assembly, with a channel in between. The magnet protection assembly surrounds the two magnet assemblies. Each magnet assembly includes: an excitation coil box, an iron core, and a energized coil. The excitation coil box has two U-shaped slots, with the iron core located in the inner slot and the energized coil in the outer slot, with both ends of the energized coil extending from the side of the excitation coil box in the same direction. By changing the current or the number of turns of the energized coil, charged ions can be flexibly deflected out of the original beamline channel. This invention can effectively filter out mixed charged ion beams, achieving purified neutral beam injection.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
High heat flow deposition component of high-power ion source discharge cavity
The invention discloses a high-heat-flow deposition component of a high-power ion source discharge cavity, which belongs to the technical field of thermal management of a neutral beam injection system of a nuclear fusion device and comprises a thermal deposition component upper plate, a thermal deposition component middle plate and a thermal deposition component lower plate which are sequentially arranged from top to bottom, grooves are formed in the upper and lower surfaces of the thermal deposition part middle plate; the thermal deposition part middle plate and the thermal deposition part upper plate are welded into a whole to form a cooling water channel; the thermal deposition component middle plate and the thermal deposition component lower plate are welded into a whole to form an air inlet channel; the air inlet channels are integrated on the two sides of the thermal deposition face of the high-heat-flow deposition component. After integral welding, an anti-electrode-pollution labyrinth structure is machined on the upper surface of the high-heat-flow deposition component, and a trapezoidal groove is formed in the outer side of the anti-electrode-pollution labyrinth structure; a magnet mounting groove is milled in the bottom of the high-heat-flow deposition component. The method solves the problems of high heat load, material thermal stress concentration and non-uniform heat dissipation of a thermal deposition part caused by upgrading and reconstruction of an ion source plan.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
Tokamak device plasma discharge starting method and system
PendingCN121601282ANuclear energy generationThermonuclear fusion reactorPlasma currentParticle physics
The invention discloses a Tokamak device plasma discharge starting method and system, and relates to the technical field of magnetic confinement fusion. The method comprises the following steps: generating initial plasma through the plasma pre-ionization system; the neutral beam injection system injects neutral particles into the initial plasma, and the injection energy is dynamically adjusted according to the plasma density monitored in real time; the electron cyclotron wave heating system injects microwave energy to drive electrons to generate plasma current; the diagnosis system monitors plasma parameters and neutral beam penetration depth in real time, and feeds back the parameters to the injection system and the heating system to adjust the parameters; and after the plasma current reaches the standard and is stable, parameters are optimized to maintain steady-state operation. The system comprises a pre-ionization module, an injection module, a heating module, a diagnosis module and a control module. According to the invention, the volt-second consumption and construction cost are reduced, the starting efficiency and stability are improved, the device is prevented from being damaged, and various magnetic confinement fusion devices are adapted.
Owner:CHINA ELECTRIC POWER RESEARCH INSTITUTE CO LTD +2
Neutral beam injection high-reliability power supply system
The invention discloses a neutral beam injection high-reliability power supply system, and belongs to the technical field of nuclear fusion device power supply. The system comprises a dual-power-supply switching module, a standby power supply module and a circuit breaker module, intelligent switching between two paths of commercial power and one path of standby power supply is realized through the dual-power-supply switching module, and a three-power-supply power supply structure is formed. The standby power supply module adopts a UPS, an EPS or a diesel generator according to load requirements, and provides electric power guarantee for precise instruments, emergency lighting and ventilation equipment and high-power loads. The system has a multi-load priority management function, switching can be completed within millisecond-level time when the mains supply breaks down, and power supply of key loads is guaranteed according to preset priorities. According to the invention, the problems of shutdown, data loss and safety caused by power supply interruption of the nuclear fusion device are effectively solved, and the reliability and continuity of a power supply system are remarkably improved.
Owner:聚变新能(安徽)有限公司 +1
A method and system for equipment failure analysis of a neutral beam injection harness system
This application discloses a method and system for fault analysis of a neutral beam injection harness system. The method includes: determining multiple fault types based on historical experimental data of the target experimental system; using the fault events of the target experimental system as the top events of a fault tree; using the multiple fault types as initial events; performing upward and downward analysis on each initial event to obtain corresponding first upper-level events and first lower-level events, and constructing a fault tree accordingly; obtaining the current fault event; determining its corresponding second upper-level events and second lower-level events based on the fault tree; determining the priority coefficients of each event in conjunction with historical experimental data and sorting them; and processing the current fault event based on the sorting results. This application can simultaneously consider fault correlation analysis and troubleshooting order determination during the harness system equipment fault analysis process, thereby improving the completeness of fault analysis and the targeting of fault location and troubleshooting.
Owner:INST OF ENERGY HEFEI COMPREHENSIVE NAT SCI CENT (ANHUI ENERGY LAB)
Neutralizer system for neutral beam injection
ActiveCN120613159ANuclear energy generationThermonuclear fusion reactorLow vacuumNeutral beam injection
The invention discloses a neutralizer system for neutral beam injection, and relates to the field of controllable nuclear fusion auxiliary heating method neutral beam injection. A neutralizer system for neutral beam injection includes a neutralizer device, an ion source, a vacuum chamber. The neutralizer device comprises a neutralizer, and the neutralizer is arranged outside the vacuum chamber and connected with the vacuum chamber. The neutralizer comprises a shell and a neutralizer body, the shell defines a containing space, the neutralizer body is contained in the containing space and comprises a plurality of heat exchange plates, the heat exchange plates are connected and jointly define a beam channel, the beam channel is located between the ion source and the vacuum chamber, liquid flow channels are formed in the heat exchange plates, and heat exchange media can circulate in the liquid flow channels. The neutralizer is arranged outside the vacuum chamber, so that the neutralizer system does not need to be subjected to vacuum breaking during maintenance, the maintenance and the installation are convenient, in addition, the internal space of the vacuum chamber can be prevented from being occupied, and the design difficulty of the vacuum chamber is reduced.
Owner:聚变新能(安徽)有限公司 +1
System and methods for forming and maintaining high energy and temperature FRC plasma via spheromak merging and neutral beam injection
A high performance field reversed configuration (FRC) system includes a central confinement chamber, two divertor chambers coupled to the chamber, and two diametrically opposed spheromak injectors coupled to the divertor chambers. A magnetic system includes quasi-de coils axially positioned along the FRC system components.
Owner:TAE TECHNOLOGIES INC
Method for simulating Tokamak INPA diagnosis passive signal
PendingCN120030776ANuclear energy generationDesign optimisation/simulationParticle flowNuclear fusion
The invention belongs to the field of magnetic confinement controllable nuclear fusion, and discloses a method for simulating Tokamak INPA to diagnose passive signals. The method comprises the following steps: firstly, calculating fast ion steady-state moderated distribution at a corresponding moment by using physical parameters of a neutral beam injection device and a temperature density profile of plasma at the corresponding moment and combining a test particle program, and then simulating distribution of neutral particles near a plasma boundary by using a boundary neutral particle simulation program; and inputting the calculated fast ion steady-state moderated distribution and boundary neutral particle distribution as input files into a fast ion diagnosis simulation program, simulating by using the fast ion diagnosis simulation program to obtain particle flux collected by INPA diagnosis in unit time, and comparing a simulation result with a measured value of INPA. According to the invention, the simulation of INPA diagnosis passive signals is realized, the experimental measurement result can be reproduced in simulation, and efficient numerical analysis is provided for the INPA diagnosis passive signals.
Owner:DALIAN UNIV OF TECH
Neutralization gas supply control method based on Monte Carlo algorithm and related product
PendingCN119227478AImprove transmission efficiencyDesign optimisation/simulationThermonuclear fusion reactorIon beamComputational physics
The invention relates to the technical field of neutral beam injection heating in the field of magnetic confinement fusion, in particular to a neutral gas supply control method based on a Monte Carlo algorithm and a related product, and the method comprises the steps: determining a target thickness, determining an initial gas target thickness, judging whether the initial gas target thickness reaches the target thickness or not, and if yes, judging that the gas supply amount is zero; if the target thickness does not reach the target thickness, gradually simulating gas supply to the neutralizer for multiple times, iteratively calculating the supplementary target thickness until the gas target thickness reaches the target thickness, obtaining the total gas supply amount, determining the total gas supply amount, and outputting the corresponding control amount; according to the method, the target thickness is obtained, the initial target thickness is calculated, then neutral supplied gas is added step by step, the supplementary target thickness is calculated iteratively in a stepping mode until the accumulated gas target thickness reaches the target thickness, and finally the control quantity is output. According to the invention, the neutralization efficiency of each ion beam can reach the optimal state by accurately controlling the air supply amount for neutralization, and the transmission efficiency of the beam is remarkably improved.
Owner:SOUTHWESTERN INST OF PHYSICS
Measurement method for core impurity density fluctuation of magnetic confinement high-temperature plasma
The invention discloses a magnetic confinement high-temperature plasma core impurity density fluctuation measurement method, which comprises the following steps: collecting an active spectrum emitted by a charge exchange reaction between a neutral beam and a high-temperature plasma impurity ion bare nucleus through an active spectrum lens; collecting a passive spectrum of a plasma area without neutral beam injection through a passive spectrum lens; respectively transmitting the active spectrum and the passive spectrum to a characteristic line radiation filtering array, and filtering the active spectrum and the passive spectrum through the characteristic line radiation filtering array; respectively transmitting the active spectrum and the passive spectrum after light filtering processing to a photodiode array for photoelectric conversion, and subtracting the photoelectric signal corresponding to the passive spectrum from the photoelectric signal corresponding to the active spectrum to obtain the photon flux of the active spectrum; and calculating the core impurity density of the magnetic confinement high-temperature plasma according to the photon flux of the active spectrum. According to the invention, the measurement of plasma core impurity density fluctuation can be obtained in an international magnetic confinement fusion device firstly.
Owner:SOUTHWESTERN INST OF PHYSICS
Diagnostic method and system for measuring potential and electric field of plasma
PCT designated stage expiredWO2025148219A1Electric discharge tubesNuclear energy generationBeam trajectoryParticle physics
The present invention relates to the technical field of neutral beam probe measurement, and provides a diagnostic method and system for measuring the potential and electric field of plasma. The method comprises: on the basis of acquired operation parameters of a magnetic confinement fusion apparatus and related parameter data of candidate particle elements, calculating signal-to-noise ratios; on the basis of the signal-to-noise ratios, selecting a neutral beam particle element, and iteratively calculating beam current trajectories of different incident energy, incident angles, and sampling areas to obtain preset parameters that enable a beam trajectory to pass through an entrance slit of an analyzer; injecting a neutral beam meeting preset parameter requirements into plasma; using the analyzer to measure primary ion beam energy of the neutral beam generated by collision ionization in a sampling area, and, on the basis of the law of conservation of energy, obtaining the potential of the sampling area; and testing different sampling areas to obtain a spatial distribution of the plasma potential and a radial electric field, so that the diagnostic ends. The beneficial effect of the present invention is that the method has extremely important significance for in-depth research of the physical mechanisms of the radial electric field and Er×B shear flow in magnetic confinement fusion plasma for suppressing turbulence and improving confinement.
Owner:SOUTHWEST JIAOTONG UNIV
Runway type Faraday shielding structure for radio frequency ion source
The invention belongs to the technical field of neutral beam injection in a controllable nuclear fusion auxiliary heating method, and discloses a runway type Faraday shielding structure for a radio frequency ion source. In the structure, a Faraday shielding cylinder comprises a runway-shaped shielding cylinder, a first water inlet pipe and a first water outlet pipe, the shielding cylinder comprises a cylinder side wall, a cylinder top wall and a first buried pipe water cooling structure, a gap is formed in the cylinder side wall, and the first water inlet pipe and the first water outlet pipe are connected with a first inlet and a first outlet of the first buried pipe water cooling structure respectively; the Faraday shielding back plate comprises a runway-shaped back plate, a second water inlet pipe and a second water outlet pipe, a second buried pipe water cooling structure is arranged in the back plate, and the second water inlet pipe and the second water outlet pipe are connected with a second inlet and a second outlet of the second buried pipe water cooling structure respectively. According to the invention, the power of the radio frequency coil can be improved, the device is suitable for a high-power and long-pulse operation system, and long-term stable operation of a high-power radio frequency electron source can be maintained.
Owner:聚变新能(安徽)有限公司 +1
System and methods for forming and maintaining high energy and temperature FRC plasma via neutral beam injection
A high performance field reversed configuration (FRC) system includes a central confinement chamber, divertors coupled to the ends of the chamber, neutral beam injectors positioned about the chamber, and a magnetic system comprising quasi-dc coils axially positioned along the FRC system components.
Owner:TAE TECHNOLOGIES INC
A neutral beam negative ion source acceleration system based on slit electrodes
The application discloses a neutral beam negative ion source accelerating system based on a slit electrode, and belongs to the field of magnetic confinement nuclear fusion neutral beam injection negative ion sources. The system comprises a plasma electrode, an extraction electrode, at least one accelerating electrode and a ground electrode which are sequentially arranged along the direction of an ion beam. The negative ion beam is extracted and accelerated by applying different potentials to the electrode plates. The application adopts a slit ground electrode and a single cooling channel water cooling structure, thereby enhancing the pumping capacity of the accelerating system, reducing the thermal load of the electrode, lowering the electrode sparking probability, and significantly improving the stability and reliability of the system.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
Simulation method for tokamak neutral beam injection and fast ion deposition
ActiveCN116127822BSimulation is accurateSolve the problem of large lossNuclear energy generationDesign optimisation/simulationNumerical stabilityIon distribution
The application discloses a simulation method for tokamak neutral beam injection and fast ion deposition. In the numerical simulation of the neutral beam particle injection and ionization process in a tokamak device, the physical parameters of the neutral beam injection device are determined first, then the injection source is simplified by using a narrow particle beam model, the neutral beam particle density of a reference point given under geometric conditions is calculated, the average free path of the neutral beam particle ionization is calculated after the parameters of the position of the reference point in the plasma interior are obtained, the ions in different regions are divided by using a non-uniform grid and are given different weights, and finally the simulation process of the neutral beam injection is realized. The application realizes the simulation of the injection process of the neutral beam particles by using the narrow particle beam model, can obtain the neutral particle and fast ion distribution at any position in the plasma, has high calculation efficiency and strong numerical stability, and is a stable and efficient numerical simulation method.
Owner:DALIAN UNIV OF TECH
Neutralizer system for neutral beam injection
This invention discloses a neutralizer system for neutral beam injection, relating to the field of neutral beam injection in controlled nuclear fusion assisted heating methods. The neutralizer system for neutral beam injection includes a neutralizer device, an ion source, and a vacuum chamber. The neutralizer device includes a neutralizer, which is located outside and connected to the vacuum chamber. The neutralizer includes a shell and a neutralizer body. The shell defines a receiving space, and the neutralizer body is housed within the receiving space and includes multiple heat exchange plates. The multiple heat exchange plates are connected and collectively define a beam channel, which is located between the ion source and the vacuum chamber. The heat exchange plates form liquid flow channels, within which a heat exchange medium can flow. By placing the neutralizer outside the vacuum chamber, maintenance and repair can be performed without breaking the vacuum in the neutralizer system, facilitating maintenance and repair, and simplifying installation. Furthermore, it avoids occupying internal space within the vacuum chamber, reducing the design complexity of the vacuum chamber.
Owner:聚变新能(安徽)有限公司 +1
A method and system for calculating the energy spectrum of nuclear fusion products under neutral beam injection conditions
ActiveCN116469479Bavoid double countingNuclear energy generationChemical processes analysis/designNuclear engineeringNuclear fusion
The application discloses a kind of nuclear fusion product energy spectrum calculation method and system under neutral beam injection condition, as follows: according to the velocity distribution function of first reactant, second reactant, N Monte Carlo samples are randomly generated, the velocity and weight of each Monte Carlo sample are obtained;According to the relative velocity of two kinds of reactants, and the mass center velocity of two kinds of reactants, the first relative motion kinetic energy of the system composed of two kinds of reactants is calculated;According to the first relative motion kinetic energy obtained, the first kinetic energy of nuclear fusion product is calculated;By introducing Dirac function and parameterized reaction cross section based on R matrix, the reaction rate coefficient of nuclear fusion product under the first kinetic energy is calculated, and the final reaction rate result is obtained by introducing the reaction rate calculation formula;According to energy box, data statistics is arranged, and the energy spectrum of nuclear fusion product is calculated.The application can accurately calculate the energy spectrum of nuclear fusion product obtained by various nuclear fusion research devices under different operation modes.
Owner:SUN YAT SEN UNIV
Neutral beam injection power feedback control method
ActiveUS20250393113A1Electric discharge tubesNuclear energy generationBeam energyNeutral beam injection
The present invention provides a neutral beam injection power feedback control method, which belongs to the field of neutral beam injection, and studies the optimal matching relationship of operating parameters of the ion source by analyzing the ion optical characteristics of a hot cathode ion source so as to expand the optimal operating range of the ion source. Based on this, linear dynamic control of injection power in a single injection cycle is completed so as to form an operation mode based on plasma feedback. The process provided by the present invention includes the following two methods. Method 1, the beam power is dynamically adjusted under constant extraction energy. Method 2, under variable extraction energy, the tracking control of probe setting value is completed to realize the dynamic adjustment of beam power under variable energy. The present invention proposes a study protocol of continuously varying beam energy or beam power in a single injection cycle discharge to develop a study of dynamic control of injection power.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES