TOKAMAK WITH POLOIDAL FIELD COIL ARRANGEMENT FOR DOUBLE NULL MERGING IGNITION, METHOD THEREFOR AND NUCLEAR FUSION REACTOR WITH THE SAME

Abstract

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.

Claims

1-12. (canceled)

13. 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.

14. A tokamak according to claim 13, wherein the shielding is further configured to shield the outer PF coil from neutrons emitted by the plasma tokamak.

15. A tokamak according to claim 14, wherein the outer PF coil is formed from high temperature superconductor, HTS.

16. A tokamak according to claim 13, wherein the outer PF coil is formed from a material which is not superconducting during operation of the outer PF coil.

17. A tokamak according to claim 16, wherein the material comprises any of: copper; aluminium; beryllium; a metal; a metal alloy.

18. A tokamak according to claim 13, 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.

19. A tokamak according to claim 13, wherein the shielding is composed of several modules such that each module extends around only a portion of the toroidal containment vessel.

20. A tokamak according to claim 13, wherein the tokamak is a spherical tokamak.

21. A tokamak according to claim 13, 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.

22. A nuclear fusion reactor comprising a tokamak according to claim 13.

23. 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.

24. A method according to claim 23, and comprising reversing a polarity of the current in each PF coil in order to aid the merging of the plasma rings.

Description

BRIEF DESCRIPTION OF THE DRAWINGS

[0018] FIGS. 1A to 1D are schematic illustrations of the stages of merging compression;

[0019] FIG. 2 illustrates the principle of a null point;

[0020] FIGS. 3A to 3D are schematic illustrations of the stages of double null merging;

[0021] FIG. 4 is a schematic illustration of a cross section of a tokamak according to an embodiment; and

[0022] FIGS. 5A to 5C are schematic illustrations of arrangements of poloidal field coils according to respective embodiments.

DETAILED DESCRIPTION

[0023] Inner and outer are used herein with reference to the radial direction of the toroidal plasma chamber, i.e. inner, inward etc. means towards the central column in a radial direction, and outer, outward etc. means away from the central column in a radial direction. These definitions are used independently of any axial separation of the components referred to. In practice, inner and outer regions can be considered as regions of high and low toroidal magnetic field, respectively, since B.sub.T1/R.

[0024] The shielding effect from the vessel wall can be reduced by placing the PF coils inside the vesselhowever, the PF coils must then be shielded from direct contact with the plasma and from the heat of the plasma, as well as from the neutrons emitted by the plasma. In a small reactor such as a spherical tokamak, the inner coil of each pair would also be located close to the plasma, resulting in similar high levels of wear to those experienced by MC coils. In order to provide a PF coil arrangement with reduced shielding from the vessel and a satisfactory level of wear, the outer coil of each pair may be placed inside the vessel, with the inner coil placed outside the vessel.

[0025] FIG. 4 shows a schematic of this arrangement. The outer coils 401 are protected from the heat and neutron emissions of the plasma 400 by a layer of shielding 402. The inner coils 403 are on the outside of the vacuum vessel 404, so do not need any additional shielding. While the shielding extends around the whole torus, the shielding blanket is typically formed of several separate modules, and therefore the image currents generated are minimal. The outer PF coils may be placed behind a layer of shielding which extends out from the vacuum vessel wall, as shown in FIG. 4, or they may be placed directly within a shielding blanket of the vacuum vesselthe latter removes the need for additional shielding, but places the outer PF coils closer to the vacuum vessel wall, which may increase the induced image currents (though less than would be present with the outer PF coil outside the vessel).

[0026] The outer coil need not be superconductingsince the current used for DNM is short lived and quickly varying, the losses incurred by using a resistive coil are minimal. Where a non-superconducting coil (e.g. copper, aluminium, beryllium, or other metal or metal alloy) is used, only limited thermal shielding is required for the outer coilsufficient to prevent structural damage to the coil (e.g. by melting). No neutron shielding is required in that case, since non-superconducting materials are likely to have sufficient lifetime even without neutron shielding. Small amounts of neutron shielding may be provided to extend the lifetime of the coil (and reduce the maintenance required), but the lifetime of the outer coil is likely to be sufficiently long that it would only need to be replaced during routine maintenance of the reactor, even if unshielded. This reduction in the shielding required allows the non-superconducting coil to be located further from the vessel wallwhich further reduces the induced image currents. Alternatively, a high temperature superconductor, HIS, outer coil may be used, though this will require neutron shielding.

[0027] The inner coils also need not be superconducting, i.e. they may be a metal or metal alloy, unless they are used for purposes other than DMN which would require a superconducting coil.

[0028] In general, the aim is for the outer coil to couple better to the plasma formed at the null points than to the vesselso that most of the power going into the coil is used to create and induce currents in the plasma, rather than to create image currents in the vessel wall. This will generally be the case when the coil is inside the vessel.

[0029] The inner PF coil may be multi-purposei.e. acting both during DNM, and during other phases of reactor operation, e.g. as a divertor coil. If so, then the location of the inner PF coil is likely to be constrained by those other purposes. The positioning of the outer PF coil (or any inner coil which is only used for DNM) is determined by the desired location and properties of the initial plasma, the loop voltage required at the null point, and any structural constraints, though by adjusting the relative current turns (coil current x number of turns) in each coil during DNM, the position of the outer PF coil can be varied somewhat.

[0030] Multiple inner coils may be used and their fields configured to position the nulls as required, in which case there is a relatively large amount of freedom in the positioning of the outer PF coils, i.e. anywhere on the low field side of the plasma vessel, in the upper or lower half (depending on which null the outer PF coil is associated with).

[0031] During the final stage of double null merging, when the plasmas actually merge, further additional inner coils may be used to push the plasmas togethereither in combination with or instead of reversing the current in the coils used to create the nulls.

[0032] FIGS. 5A to 5C show three exemplary arrangements of the PF coils. In each figure, the upper and lower half of the plasma vessel each have an outer PF coil 501 and first and second inner PF coils 502, 503. In FIG. 5A, only the first inner PF coil is used for DNM, and so the null 504 is positioned between the first inner PF coil and the outer PF coil (in practice, there will be some variation due to other magnetic fields). In FIG. 5B, the second inner PF coil is also used for DNM. By varying the relative field strengths of the first and second inner PF coil and the outer PF coil, the position of the null 504 can be controlled over a wider range than with just two coils. In this case, the second PF coil is used to push the null away from the wall of the vacuum vessel (allowing for larger, more stable initial plasmas). FIG. 5C shows an arrangement where the null 504 is located in the same place as FIG. 5B, but the outer PF coil is in a different location, with the field strengths of each coil adjusted to compensate for this.

[0033] It will be appreciated by the person of skill in the art that various modifications may be made to the above described embodiments without departing from the scope of the invention.