Tokamak with poloidal field coil arrangement for double null merging ignition, method therefor and nuclear fusion reactor with the same

US10580535B2 · US · B2

Patent metadata
FieldValue
Publication numberUS-10580535-B2
Application numberUS-201816481903-A
CountryUS
Kind codeB2
Filing dateJan 29, 2018
Priority dateJan 30, 2017
Publication dateMar 3, 2020
Grant dateMar 3, 2020

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  1. Title

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  2. Abstract

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  3. Assignees and inventors

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  4. Key dates

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  5. First independent claim

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  6. CPC / IPC classifications

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  7. Citations and related patents

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Abstract

Official abstract text for this publication.

A tokamak comprising a toroidal containment vessel and a plasma initiation system. The toroidal containment vessel is configured to contain a plasma. The plasma initiation system comprises upper and lower poloidal field, PF, coil sets. Each PF coil set comprises at least one inner PF coil located outside of the containment vessel, an outer PF coil located inside the containment vessel, and shielding located between the outer PF coil and a location of the plasma during operation of the tokamak and configured to protect the outer PF coil from heat emitted by the plasma. The inner and outer PF coils are configured so as to form a PF null within the containment vessel between the inner and outer PF coils, such that the upper and lower PF coil pairs are operable to initiate a plasma in the containment vessel via double null merging.

First claim

Opening claim text (preview).

The invention claimed is: 1. A tokamak comprising: a toroidal containment vessel configured to contain a plasma; a plasma initiation system comprising upper and lower poloidal field, PF, coil sets, each PF coil set comprising: at least one inner PF coil located outside the containment vessel; an outer PF coil located inside the containment vessel; wherein the inner PF coil is located radially inward of the outer PF coil; shielding located between the outer PF coil and a location of the plasma during operation of the tokamak and configured to protect the outer PF coil from heat emitted by the plasma; the inner and outer PF coils being configured so as to form a PF null within the containment vessel between the inner and outer PF coils, such that the upper and lower PF coil pairs are operable to initiate a plasma in the containment vessel via double null merging. 2. A tokamak according to claim 1 , wherein the shielding is further configured to shield the outer PF coil from neutrons emitted by the plasma tokamak. 3. A tokamak according to claim 2 , wherein the outer PF coil is formed from high temperature superconductor, HTS. 4. A tokamak according to claim 1 , wherein the outer PF coil is formed from a material which is not superconducting during operation of the outer PF coil. 5. A tokamak according to claim 4 , wherein the material comprises any of: copper; aluminium; beryllium; a metal; a metal alloy. 6. A tokamak according to claim 1 , wherein the outer PF coil is located within a shielding blanket of the containment vessel, and wherein said shielding located between the outer PF coil and the location of the plasma is a part of said shielding blanket. 7. A tokamak according to claim 1 , wherein the shielding is composed of several modules such that each module extends around only a portion of the toroidal containment vessel. 8. A tokamak according to claim 1 , wherein the tokamak is a spherical tokamak. 9. A tokamak according to claim 1 , wherein the outer PF coil is configured to magnetically couple better to a plasma located at the PF null than to the containment vessel, such that when power is applied to the PF coil, a proportion of the power which results in creation and induction of currents in the plasma, is greater than a proportion of the power which results in creation and induction of currents in the containment vessel. 10. A nuclear fusion reactor comprising a tokamak according to claim 1 . 11. A method of initiating plasma within a tokamak, wherein the tokamak comprises a toroidal containment vessel configured to contain a plasma, a plasma initiation system comprising upper and lower poloidal field, PF, coil sets, each PF coil set comprising at least one inner PF coil located outside of the containment vessel and an outer PF coil located inside the containment vessel, the method comprising: creating upper and lower PF nulls using the respective upper and lower PF coil sets by passing respective constant currents through each coil of each set; reducing the current in each PF coil in order to generate a loop voltage at the PF nulls and create a plasma ring at each null; the plasma rings merging to form a single plasma. 12. A method according to claim 11 , and comprising reversing a polarity of the current in each PF coil in order to aid the merging of the plasma rings.

Assignees

Inventors

Classifications

  • G21B1/057Primary

    Tokamaks · CPC title

  • Details · CPC title

  • H05H1/12Primary

    wherein the containment vessel forms a closed or nearly closed loop {(G21B1/05 takes precedence)} · CPC title

  • Nuclear fusion reactors · CPC title

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What does patent US10580535B2 cover?
A tokamak comprising a toroidal containment vessel and a plasma initiation system. The toroidal containment vessel is configured to contain a plasma. The plasma initiation system comprises upper and lower poloidal field, PF, coil sets. Each PF coil set comprises at least one inner PF coil located outside of the containment vessel, an outer PF coil located inside the containment vessel, and shie…
Who is the assignee on this patent?
Tokamak Energy Ltd
What technology area does this patent fall under?
Primary CPC classification G21B1/057. Mapped technology areas include Physics.
When was this patent published?
Publication date Tue Mar 03 2020 00:00:00 GMT+0000 (Coordinated Universal Time) (B2). Legal status and post-grant events are not shown on this page.
What related patents are in patentsdb?
We list 8 related publications on this page (citations in our corpus or others sharing the same primary CPC).