FIELD COIL WITH EXFOLIATED TAPE
    1.
    发明申请

    公开(公告)号:WO2019038526A1

    公开(公告)日:2019-02-28

    申请号:PCT/GB2018/052355

    申请日:2018-08-20

    Abstract: There is disclosed a toroidal field coil for use in a spherical tokamak. The toroidal field coil comprises a central column and a plurality of return limbs. The central column comprises a plurality of exfoliated HTS tapes, and the return limbs comprise a plurality of substrated HTS tapes. Each exfoliated HTS tape comprises a ReBCO layer bonded to respective metal interface layers on each side of the ReBCO layer, each metal interface layer being bonded to a metal stabiliser layer. Each substrated HTS tape comprises a ReBCO layer bonded on one side to a metal interface layer and on the other side to an oxide buffer stack, the metal interface layer being bonded to a metal stabiliser layer and the oxide buffer stack being bonded to a substrate.

    SPHERICAL TOKAMAK WITH HIGH POWER GAIN RATIO

    公开(公告)号:WO2021191030A1

    公开(公告)日:2021-09-30

    申请号:PCT/EP2021/056868

    申请日:2021-03-17

    Abstract: A tokamak fusion reactor. The tokamak fusion reactor comprises a toroidal plasma chamber and a plasma confinement system arranged to generate a magnetic field for confining a plasma in the plasma chamber. The plasma confinement system comprises toroidal field magnets, which generate a magnetic field, BT0, in the centre of the plasma. The toroidal field magnets are configured such that, in use, the magnetic field, on conductor of the toroidal field magnets is at least 20 Tesla. The plasma confinement system is configured such that, in use, the plasma has: an aspect ratio, A, of 2 or less; an elongation, K, of at least 2; a major radius R0 of 3.5 meters or less; a normalised beta of at least 3; an engineering safety factor, qeng, of at least 2.0; wherein the engineering safety factor qeng is defined as: qeng = 5 BT0R0K/A2IP where Ip is the plasma current; a ratio of the fusion gain, Qfus to the fusion power, Pfus, greater than 0.03MW-1 at fusion power, Pfus, less than 500MW

    TOROIDAL FIELD COIL FOR USE IN A FUSION REACTOR
    3.
    发明申请
    TOROIDAL FIELD COIL FOR USE IN A FUSION REACTOR 审中-公开
    用于熔融反应器的电磁场线圈

    公开(公告)号:WO2015036749A1

    公开(公告)日:2015-03-19

    申请号:PCT/GB2014/052738

    申请日:2014-09-10

    CPC classification number: G21B1/057 H01F6/06 Y02E30/122 Y02E30/128

    Abstract: Disclosed herein is a toroidal field coil for generating a toroidal magnetic field in a nuclear fusion reactor comprising a toroidal plasma chamber having a central column, the toroidal field coil comprising a plurality of windings passing through the central column and around the outside of the plasma chamber. Each winding includes a cable comprising a plurality of stacked HTS tapes, each HTS tape including one or more layers of a high temperature superconductor material. The HTS tapes are arranged such that a face of each HTS tape is parallel to the toroidal magnetic field as the cable passes through the centre column

    Abstract translation: 本文公开了一种用于在核聚变反应堆中产生环形磁场的环形场线圈,其包括具有中心柱的环形等离子体室,环形场线圈包括穿过中心柱并且围绕等离子体室外部的多个绕组 。 每个绕组包括包括多个堆叠的HTS带的电缆,每个HTS带包括一层或多层高温超导体材料。 HTS带布置成使得当电缆穿过中心柱时,每个HTS带的表面平行于环形磁场

    HYBRID MAGNET FOR USE IN FUSION REACTORS
    4.
    发明申请
    HYBRID MAGNET FOR USE IN FUSION REACTORS 审中-公开
    用于熔融反应器的混合磁体

    公开(公告)号:WO2016027058A1

    公开(公告)日:2016-02-25

    申请号:PCT/GB2015/052142

    申请日:2015-07-24

    Abstract: A toroidal field coil for generating a toroidal magnetic field in a nuclear fusion reactor comprising a toroidal plasma chamber having a central column. The toroidal field coil comprises a portion passing through the central column. The portion passing through the central chamber comprises: • a low temperature superconductor, LTS, layer (21) formed from LTS; • a high temperature superconductor, HTS, layer (22) formed from HTS and located radially outward of the LTS layer. • a non-superconducting conductive layer (23) formed from electrically conducting, non-superconducting material and located radially outward of the HTS and LTS layers.

    Abstract translation: 一种用于在核聚变反应堆中产生环形磁场的环形场线圈,其包括具有中心柱的环形等离子体室。 环形场线圈包括通过中心柱的部分。 穿过中央室的部分包括:•低温超导体,LTS,由LTS形成的层(21); •高温超导体,HTS,由HTS形成并位于LTS层径向外侧的层(22)。 •由导电的非超导材料形成并位于HTS和LTS层的径向外侧的非超导导电层(23)。

    EFFICIENT COMPACT FUSION REACTOR
    6.
    发明申请
    EFFICIENT COMPACT FUSION REACTOR 审中-公开
    有效的紧凑型熔融反应器

    公开(公告)号:WO2015155531A1

    公开(公告)日:2015-10-15

    申请号:PCT/GB2015/051078

    申请日:2015-04-09

    Abstract: An efficient compact nuclear fusion reactor for use as a neutron source or energy source is described. The reactor comprises a toroidal plasma chamber and a plasma confinement system arranged to generate a magnetic field for confining a plasma in the chamber. The plasma confinement system is configured so that a major radius of the confined plasma is 1.5m or less. The toroidal magnetic field is operated 5T or less and the plasma current is 5 MA or less. Despite this, α-particles generated are confined in the plasma.

    Abstract translation: 描述了用作中子源或能源的有效的紧凑型核聚变反应堆。 反应器包括环形等离子体室和等离子体约束系统,其被布置成产生用于限制室中的等离子体的磁场。 等离子体限制系统构造成使得约束等离子体的主半径为1.5μm以下。 环形磁场运行5T以下,等离子体电流为5MA以下。 尽管如此,产生的α-粒子被限制在等离子体中。

    MACHINE LEARNING IN FUSION REACTORS
    7.
    发明申请

    公开(公告)号:WO2019008349A1

    公开(公告)日:2019-01-10

    申请号:PCT/GB2018/051874

    申请日:2018-07-04

    Abstract: A method of controlling a plasma in a nuclear fusion reactor. The nuclear fusion reactor comprises sensors and plasma control inputs. An initial control model is provided, relating readings of at least a subset of the sensors to control of the plasma control inputs. A control loop is performed, comprising: operating the plasma control inputs in dependence upon the sensors according to the control model; determining correlations between readings of each of the sensors, and/or between readings of the sensors and states of the plasma control inputs; and adjusting the control model based on the determined correlations.

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