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20 results about "Neutral beam injection" patented technology
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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).
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
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
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)
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
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
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
A neutral beam injection negative ion source high-energy exit electron protection device
PendingCN122158197ANuclear energy generationThermonuclear fusion reactorNuclear fusionHeat deposition
The application discloses a high-energy outgoing electron protection device for a neutral beam injection negative ion source, belongs to the field of the neutral beam injection negative ion source of magnetic confinement nuclear fusion, and mainly comprises a protection plate, a supporting base, a thermocouple and an infrared thermal imager. The protection plate is used for intercepting high-energy outgoing electrons. The supporting base is used for mounting and positioning the protection plate in a beam line vacuum chamber. The thermocouple is used for realizing real-time monitoring of the local temperature of the protection plate. The infrared thermal imager is used for observing a large-area heat source of the protection plate and determining the heat deposition position distribution of the high-energy outgoing electrons. The application realizes protection of heat load sensitive components such as a cryogenic pump by intercepting the high-energy outgoing electron beam and monitoring the deposition position of the high-energy outgoing electron beam, promotes the performance improvement and scheme perfection of an electron suppression means, is favorable for long-pulse stable operation of the negative ion source, and can effectively protect the high-energy outgoing electron in the neutral beam injection negative ion source.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
Long-pulse neutral beam ion source filament arc current supply system and control method
The application discloses a long-pulse neutral beam ion source filament arc current power supply system and a control method, and relates to the technical field of neutral beam injection and plasma ion source power supply. The system comprises an ion source body, a grouped power supply array and a central control unit. The ion source body is internally provided with a filament. The grouped power supply array comprises N groups of power supply units, each group of power supply units comprises an independent filament power supply unit and an arc current power supply unit, and each group of power supply units is connected in parallel to the filament of the ion source body. The central control unit is in communication connection with the filament power supply units and the arc current power supply units of each group, and is configured to control the groups of power supply units to alternately operate, so as to alternately heat and supply power to the filament. According to the application, the same filament is connected in parallel by the multiple groups of power supply units, and the central control unit controls the groups of power supply units to alternately operate, so that the thermal load is balanced to prolong the service life of the filament. Meanwhile, the groups of power supply units are alternately powered, the plasma is continuously extracted, the discharge pulse width is improved, and the long-pulse operation requirement of magnetic confinement nuclear fusion is met.
Owner:SOUTHWESTERN INST OF PHYSICS
Neutral beam injector ignition adaptive recovery control system and method
PendingCN121662433ANuclear energy generationThermonuclear fusion reactorControl systemControl engineering
The invention provides a neutral beam injector ignition adaptive recovery control system and method, and belongs to the technical field of nuclear fusion experiment device control and fault diagnosis, and the system comprises a channel independent configuration module which is used for configuring ignition recovery parameters for each power channel in a neutral beam injector; the real-time monitoring and diagnosis module is used for collecting a voltage signal and a current signal of each power supply channel in real time, diagnosing a sparking event of the power supply channel, obtaining a fault channel and performing sparking counting on each fault channel; the safety cut-off module cuts off the fault channel; and the distributed control module is used for respectively controlling each fault channel to recover operation according to the ignition times and the ignition recovery parameters corresponding to the fault channels. According to the method, breakthrough progress is achieved in multiple dimensions such as real-time performance, control precision and system reliability, and a superior-performance, safe and reliable frontier solution is provided for the control field of the neutral beam injector and even the whole nuclear fusion device.
Owner:INST OF ENERGY HEFEI COMPREHENSIVE NAT SCI CENT (ANHUI ENERGY LAB)
Ion swallowed device and neutral beam injection system
ActiveCN121862487ARadiation/particle handlingNuclear energy generationParticle physicsNeutral beam injection
The invention relates to the technical field of nuclear fusion, and discloses an ion swallowing device and a neutral beam injection system, the ion swallowing device is used for absorbing high-energy ions, and the ion swallowing device comprises a mounting rack; the first energy absorption target, the second energy absorption target and the third energy absorption target are all fixed to the mounting frame, the first energy absorption target and the third energy absorption target are opposite and spaced in the first direction, the second energy absorption target is arranged between the first energy absorption target and the third energy absorption target, the first energy absorption target is used for absorbing first energy ions, and the third energy absorption target is used for absorbing second energy ions. The second energy absorption target is used for absorbing second energy ions, and the third energy absorption target is used for absorbing third energy ions. Through the arrangement of the first energy absorption target, the second energy absorption target and the third energy absorption target, the absorption efficiency of the ion swallowing device on deflected ions can be improved, and the risk that the ions in the ion swallowing device escape into the vacuum chamber to cause damage to other parts in the vacuum chamber can be reduced.
Owner:聚变新能(安徽)有限公司 +1
Method for filtering magnetic field through multichannel current of high-power negative ion source
PendingCN122067817ANuclear energy generationThermonuclear fusion reactorNeutral beam injectionMechanical engineering
The invention discloses a high-power negative ion source multichannel current filtering magnetic field method, which belongs to the technical field of nuclear fusion neutral beam injection, and comprises the following steps: designing and optimizing a plasma electrode of a high-power negative ion source multichannel current filtering magnetic field device: forming a resistance balance groove in one surface, facing an extraction electrode, of the plasma electrode; designing an independent cooling water path: separating the plasma electrode from a cooling water inlet pipeline and a cooling water return pipeline of other parts, and arranging an independent flow meter and a temperature sensor; and debugging a power supply function and a current control function of a filtering magnetic field power supply of the high-power negative ion source multi-channel current filtering magnetic field device to obtain an optimal filtering magnetic field current parameter under different plasma parameter conditions so as to guide a long pulse operation experiment. According to the invention, a more uniform and stronger filtering magnetic field can be generated, and the electron temperature of the area near the leading-out surface of the high-power negative ion source is effectively reduced.
Owner:HEFEI INSTITUTE OF PHYSICAL SCIENCE CHINESE ACADEMY OF SCIENCES
Runway-type faraday shield structure for radio frequency ion source
The application belongs to the technical field of neutral beam injection in the controllable nuclear fusion auxiliary heating method, and discloses a racetrack type Faraday shielding structure for a radio frequency ion source. In the structure, the Faraday shielding cylinder comprises a racetrack type 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, the cylinder side wall is provided with a gap, 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 racetrack type 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. The application can improve the power of the radio frequency coil, is suitable for a high-power and long-pulse operation system, and can maintain the long-term stable operation of the high-power radio frequency electron source.
Owner:聚变新能(安徽)有限公司 +1