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公开(公告)号：US12207384B2
公开(公告)日：2025-01-21
申请号：US18056741
申请日：2022-11-18
Applicant: Anhui Agricultural University
Inventor： Yaoyao Wang , Qing Zhou , Zhenxing Wang , Chengzhou Liu , Wendong Ma , Liang Zhu , Jiafang Shan
Abstract: Disclosed is a top surface wave antenna of a spherical Tokamak, comprising a feedback waveguide, a brim, sub-waveguides, and a metal base. The lower end of the feed waveguide is connected to one end of the metal base, and one side of the feed waveguide is connected to the brim. The brim is towards a length direction of the metal base. A plurality of sub-waveguides are arranged on the metal base at equal intervals, the tops of the sub-waveguides are not higher than the height of the metal base, and the sub-waveguides are arranged in a rising line trend. The feed waveguide serves as a microwave input port. The top surface wave antenna of the spherical Tokamak is mainly used in a high-power Tokamak system and acts on the low-hybrid wave current driving together with an external antenna so as to obtain a better effect.
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公开(公告)号：US20240404713A1
公开(公告)日：2024-12-05
申请号：US18793320
申请日：2024-08-02
Applicant: Samuel Pierre Moss, II
Inventor： Samuel Pierre Moss, II
Abstract: A fusion reactor with a spherical shaped confinement apparatus comprising a plurality of conductive coils that form a rotating negative potential well about a confined center at the center of the system, confining electrons expelled from a surrounding electron discharging grid to obtain a curved spherical rotation pattern to the electrons confined with in the confinement apparatus. The confinement apparatus is also rotated by a multipolar rotating electric machine to promote improved confinement by reducing the amount of time for electrons to escape confinement and shaping the particles in a more curved and spherical shape to allow converging and diverging geodesic effects to enhance tighter and denser particle confinement. This fusion concept reduces the amount of energy needed to operate while minimizing magnetic reconnection disturbances, allowing the NESAR to be the world's first reactor to meet the break-even point of fusion with possible gravitational effects.
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公开(公告)号：US20240395446A1
公开(公告)日：2024-11-28
申请号：US18789978
申请日：2024-07-31
Applicant: THE TRUSTEES OF PRINCETON UNIVERSITY
Inventor： DAVID GATES , KENNETH HAMMOND , CAOXIANG ZHU
Abstract: The present disclosure provides methods for defining a magnet array for a stellarator. In some embodiments, the magnet array, once defined, comprises a plurality of permanent magnets, where each permanent magnet of the plurality of permanent magnets is selected from a set of predetermined permanent magnet types. In some embodiments, each predetermined permanent magnet type in the set of predetermined permanent magnet types has a predetermined shape (geometry) and/or predetermined orientation angles (also known as a polarization orientation).
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公开(公告)号：US20240387063A1
公开(公告)日：2024-11-21
申请号：US18318391
申请日：2023-05-16
Applicant: Commonwealth Fusion Systems LLC
Inventor： Brandon N. Sorbom , Robert Mumgaard , Daniel Brunner , Alexander Creely , Cody Dennett , Matthew Vernacchia , Caroline Sorensen , Theodore Wyeth
Abstract: Techniques are described for automatically removing and replacing components, including a vacuum vessel, from a tokamak. The inventors have recognized that schemes for automatically removing and replacing components from a tokamak should preferably be simple (e.g., using proven equipment to perform a series of non-mechanically complex tasks) and have a very low risk of damaging components. Techniques described herein may include splitting a tokamak into multiple pieces, separating the pieces, and removing the now separate pieces of the vacuum vessel from within the pieces of the tokamak. A new vacuum vessel can be inserted in multiple pieces and the tokamak rejoined to complete the replacement process.
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公开(公告)号：US20240274304A1
公开(公告)日：2024-08-15
申请号：US18562305
申请日：2023-05-23
Applicant: Charles Spencer Pitcher
Inventor： Charles Spencer Pitcher
Abstract: All magnetic nuclear fusion devices face common technical challenges related to power and particle control arising from the close proximity of a thermonuclear plasma to the plasma-facing component. The plasma-facing component is subjected to high incident power density and erosion processes, and must facilitate the efficient remove of the fusion-ash. In the past, limiters and divertors have been used in magnetic fusion devices for this purpose. These are discussed and extended to a new concept, the “stochastic mantle”, which utilizes a stochastic magnetic field layer to disperse power on the plasma-facing component to the maximum extent possible. Further, if operated at sufficient plasma collisionality, it reduces the energy of particles incident on the plasma-facing component, globally reducing erosion by physical sputtering, while producing high gas pressures for fusion-ash removal through pumping ducts. The approach is particular suited for stellarators, but others devices may be considered.
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Patent Agency Ranking
公开(公告)号：US20240212994A1
公开(公告)日：2024-06-27
申请号：US18510456
申请日：2023-11-15
Applicant: ZAP ENERGY, INC.
Inventor： Peter H. Stoltz , Eric T. Meier , Uri Shumlak , Brian A. Nelson
CPC classification number: H01J37/3266 , H01J37/32064 , G21B1/05 , G21B1/21
Abstract: Methods and systems are provided for increasing energy output from Z-pinch and other plasma confinement systems. In one example, a system may include memory storing instructions that, if executed by one or more processors, cause the system to adjust one or more parameters to generate a magnetic field which is sufficiently strong to axially compress a fuel gas to induce thermonuclear fusion and increase a fusion energy gain factor greater than a fusion energy gain factor limit attainable by the thermonuclear fusion. In certain examples, adjusting the one or more parameters may include adjusting a duty cycle of a discharge current applied to the fuel gas based, at least in part, on an amount of thermal collisions between fusion byproducts and the fuel gas. In certain examples, by adjusting the duty cycle, the magnetic field may be adjusted to induce or increase the thermal collisions.
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公开(公告)号：US20240177874A1
公开(公告)日：2024-05-30
申请号：US18395510
申请日：2023-12-23
Applicant: THE TRUSTEES OF PRINCETON UNIVERSITY
Inventor： DAVID GATES , CAOXIANG ZHU , KENNETH HAMMOND
Abstract: Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.
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公开(公告)号：US20240153651A1
公开(公告)日：2024-05-09
申请号：US18415840
申请日：2024-01-18
Applicant: THE TRUSTEES OF PRINCETON UNIVERSITY
Inventor： David Gates
Abstract: Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.
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公开(公告)号：US20240096510A1
公开(公告)日：2024-03-21
申请号：US18484009
申请日：2023-10-10
Applicant: ADAM S. GOLDBERG
Inventor： ADAM S. GOLDBERG
Abstract: 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.
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公开(公告)号：US20240079151A1
公开(公告)日：2024-03-07
申请号：US18256760
申请日：2021-12-10
Applicant: FUSE ENERGY TECHNOLOGIES CORP.
Inventor： Raymond GOLINGO , Jean-Christoph BTAICHE , Paul HARRIS , Ayan CHOUDHURY , Zahra SEIFOLLAHI MOGHADAM , Pierre TOCHON
Abstract: Plasma processing systems and methods for fusion power applications are disclosed. The system can include a plasma confinement device including a reaction chamber; a plasma formation and injection device configured to form a source plasma outside the reaction chamber and inject the source plasma inside the reaction chamber; and a power supply configured to supply power to the plasma confinement device to apply a voltage across the reaction chamber to compress the source plasma into a Z-pinch plasma capable of sustaining fusion reactions. The plasma confinement device can include an inner electrode surrounded by an outer electrode to define therebetween an acceleration region of the reaction chamber. The outer electrode can extend beyond the inner electrode to define an assembly region of the reaction chamber. The source plasma can be injected in the acceleration region and flowed into the assembly region to be compressed into the Z-pinch plasma.
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