-
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
Applicant: TOKAMAK ENERGY LTD
Inventor: BRITTLES, Greg , KINGHAM, David , SLADE, Robert
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.
-
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
Applicant: TOKAMAK ENERGY LTD
Inventor: COSTLEY, Alan , KINGHAM, David
IPC: G21B1/05
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
-
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
Applicant: TOKAMAK ENERGY LTD
Inventor: SYKES, Alan , GRYAZNEVICH, Mikhail , KINGHAM, David , HAWKSWORTH, David , MELHEM, Ziad , BALL, Steven
IPC: G21B1/05
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
-
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
Applicant: TOKAMAK ENERGY LTD
Inventor: KINGHAM, David , GRYAZNEVICH, Mikhail
CPC classification number: G21B1/057 , G21B1/17 , H01F6/06 , H05H1/12 , H05H1/16 , Y02E30/122 , Y02E30/126 , Y02E30/128
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)。
-
公开(公告)号:WO2016009176A1
公开(公告)日:2016-01-21
申请号:PCT/GB2015/051961
申请日:2015-07-07
Applicant: TOKAMAK ENERGY LTD
Inventor: KINGHAM, David , SMITH, George
CPC classification number: G21B1/13 , C22C29/005 , C22C29/02 , C22C29/14 , G21B1/057 , G21F1/08 , G21Y2004/10 , Y02E30/122 , Y02E30/128
Abstract: There is described neutron shielding for a nuclear fusion reactor. The neutron shielding includes a cemented carbide or boride comprising a binder and an aggregate, the aggregate comprising particles of a carbide or boride compound.
Abstract translation: 描述了用于核聚变反应堆的中子屏蔽。 中子屏蔽包括包含粘合剂和骨料的硬质合金或硼化物,所述骨料包含碳化物或硼化物化合物的颗粒。
-
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
Applicant: TOKAMAK ENERGY LTD
Inventor: SYKES, Alan , GRYAZNEVICH, Mikhail , KINGHAM, David
CPC classification number: G21B1/057 , G21Y2004/305 , H05H1/12 , Y02E30/122 , Y02E30/126 , Y02E30/128
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。
-
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
Applicant: TOKAMAK ENERGY LTD
Inventor: MCNAMARA, Steven Antony Milton , BUXTON, Peter , KINGHAM, David
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.
-
-
-
-
-
-