Stochastic Mantle for Magnetic Fusion Devices

    公开(公告)号:US20240274304A1

    公开(公告)日:2024-08-15

    申请号:US18562305

    申请日:2023-05-23

    IPC分类号: G21B1/05 G21B1/13 G21B1/17

    CPC分类号: G21B1/055 G21B1/13 G21B1/17

    摘要: 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.

    METHODS AND SYSTEMS FOR INCREASING ENERGY OUTPUT IN Z-PINCH PLASMA CONFINEMENT SYSTEM

    公开(公告)号:US20240212994A1

    公开(公告)日:2024-06-27

    申请号:US18510456

    申请日:2023-11-15

    申请人: ZAP ENERGY, INC.

    IPC分类号: H01J37/32 G21B1/05 G21B1/21

    摘要: 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.

    PLANAR COIL STELLARATOR
    3.
    发明公开

    公开(公告)号:US20240177874A1

    公开(公告)日:2024-05-30

    申请号:US18395510

    申请日:2023-12-23

    IPC分类号: G21B1/05 H01F6/06

    CPC分类号: G21B1/055 H01F6/06

    摘要: 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.

    PLANAR COIL STELLARATOR
    4.
    发明公开

    公开(公告)号:US20240153651A1

    公开(公告)日:2024-05-09

    申请号:US18415840

    申请日:2024-01-18

    发明人: David Gates

    IPC分类号: G21B1/05 H01F6/06

    CPC分类号: G21B1/055 H01F6/06

    摘要: 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.

    REACTOR FOR PRODUCING A NUCLEAR FUSION REACTION

    公开(公告)号:US20240096510A1

    公开(公告)日:2024-03-21

    申请号:US18484009

    申请日:2023-10-10

    申请人: ADAM S. GOLDBERG

    发明人: ADAM S. GOLDBERG

    摘要: 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.

    PLASMA INJECTION AND CONFINEMENT SYSTEMS AND METHODS

    公开(公告)号:US20240079151A1

    公开(公告)日:2024-03-07

    申请号:US18256760

    申请日:2021-12-10

    IPC分类号: G21B1/05 H05H1/54

    CPC分类号: G21B1/05 H05H1/54 G21B1/21

    摘要: 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.

    System Of Converging Plasma Pistons
    9.
    发明公开

    公开(公告)号:US20240015876A1

    公开(公告)日:2024-01-11

    申请号:US18353509

    申请日:2023-07-17

    发明人: James J. Connell

    摘要: A magnetic confinement system includes a magnetic mirror device that includes a chamber to hold a target plasma and a coil arrangement to generate a magnetic field configuration in the chamber to confine the target plasma in cylindrically-symmetric form in the chamber, the magnetic field configuration having open ends. The magnetic confinement system further includes plasma guns to generate plasma pistons and project the plasma pistons at the open ends of the magnetic field configuration. In operation, the plasma pistons converge towards each other to close the open ends of the magnetic field configuration and to compress and heat the target plasma.

    Hohlraum used as a single turn solenoid to generate seed magnetic field for inertial confinement fusion

    公开(公告)号:US11783952B2

    公开(公告)日:2023-10-10

    申请号:US17644292

    申请日:2021-12-14

    IPC分类号: G21B1/05 G21B1/03 G21B1/19

    摘要: Application of axial seed magnetic fields in the range 20-100 T that compress to greater than 10,000 T (100 MG) under typical NIF implosion conditions may significantly relax the conditions required for ignition and propagating burn in NIF ignition targets that are degraded by hydrodynamic instabilities. Such magnetic fields can: (a) permit the recovery of ignition, or at least significant alpha particle heating, in submarginal NIF targets that would otherwise fail because of adverse hydrodynamic instability growth, (b) permit the attainment of ignition in conventional cryogenic layered solid-DT targets redesigned to operate under reduced drive conditions, (c) permit the attainment of volumetric ignition in simpler, room-temperature single-shell DT gas capsules, and (d) ameliorate adverse hohlraum plasma conditions during laser drive and capsule compression. In general, an applied magnetic field should always improve the ignition condition for any NIF ignition target design.