Efficient compact fusion reactor
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 1.5 m or less. The reactor is constructed using high temperature superconducting toroidal magnets, which may be operated at low temperature (77K or lower) to provide enhanced performance. The toroidal magnetic field can be increased to 5 T or more giving significant increases in fusion output, so that neutron output is very efficient and the reactor can produce a net output of energy.
1. A compact nuclear fusion reactor comprising a spherical tokamak having a toroidal plasma chamber and a plasma confinement system arranged to generate a magnetic field for confining a plasma in the plasma chamber, wherein:
the plasma confinement system is configured so that the major radius of the confined plasma is 1.5 m or less;
the plasma confinement system includes toroidal field magnets having toroidal field coils made from material comprising high temperature superconductor, the toroidal field magnets being configured such that the magnetic field includes a toroidal component of at least 5 T;
the spherical tokamak comprises a cryostat configured to cool the high temperature superconductor to 30K or less;
wherein the high temperature superconductor is BSCCO or (Re)BCO.
2. The fusion reactor of claim 1 , wherein the plasma includes tritium ions.
3. The fusion reactor of claim 1 , wherein the plasma includes deuterium ions but not tritium ions.
4. The fusion reactor of claim 1 , arranged to ramp up the plasma current using one or more of the following operations:
activation of a one or more solenoids;
RF current drive; and
heating the plasma so that a rapid increase in poloidal field necessary to contain the plasma as it grows inputs almost sufficient flux to ramp up a plasma current to a desired working value.
5. The fusion reactor of claim 4 , wherein the one or more solenoids are retractable.
6. The fusion reactor of claim 1 in which one or more of a cryostat casing and material from which the toroidal field magnets are constructed is configured to provide structural integrity.
7. The fusion reactor of claim 1 comprising a central column formed from beryllium or aluminium.
8. The fusion reactor of claim 1 in which an inner part of a central column is made of HTS and an outer part is made of beryllium or aluminium.
9. The fusion reactor of claim 7 , wherein the beryllium or aluminium is cryogenically cooled to reduce its resistance and is joined to HTS material forming the remainder of the toroidal field magnets apart from the central column.
10. The fusion reactor of claim 1 , further comprising divertors optimised to reduce the load per unit area on the walls of the plasma chamber.
11. The fusion reactor of claim 10 , wherein part or all of the surface of the divertors is coated with lithium.
12. The fusion reactor of claim 1 , wherein part or all of the surface of the plasma facing wall is coated with lithium.
13. A power station comprising a plurality of fusion reactors as claimed in claim 1 .
14. The fusion reactor of claim 1 , wherein the material comprising high temperature superconductor comprises one or more tapes, each tape comprising:
a substrate layer;
a plurality of buffer stack layers;
a layer of the high temperature superconductor.
15. The fusion reactor of claim 14 , wherein each tape further comprises:
a silver layer;
first and second copper stabiliser layers, located on respective sides of the tape.
16. The fusion reactor of claim 1 , wherein the high temperature superconductor is a material which has superconducting properties at temperatures above about 30 K in a low magnetic field.
17. The fusion reactor of claim 1 , wherein the toroidal component is between 5 T and 15 T.