A plasma confinement device (500), comprises a first magnet system (1) comprising a first plurality of concentrically arranged circular-loop coils (11, 12), comprising a first coil (11) arranged to carry a current in a first direction; and a second coil (12) arranged to carry a current in a second direction opposite to the first direction; and a second magnet system (2) comprising a second plurality of concentrically arranged circular-loop coils (21, 22), arranged with mirror symmetry with respect to the first magnet system (1) relative to a symmetry plane (P) located between the first magnet system (1) and the second magnet system (2), creating an annular plasma confinement area (206) at the symmetry plane (P) with a magnetic field normal to the symmetry plane (P) at the symmetry plane (P).

A plasma confinement device (500), comprises a first magnet system (1) comprising a first plurality of concentrically arranged circular-loop coils (11, 12), comprising a first coil (11) arranged to carry a current in a first direction; and a second coil (12) arranged to carry a current in a second direction opposite to the first direction; and a second magnet system (2) comprising a second plurality of concentrically arranged circular-loop coils (21, 22), arranged with mirror symmetry with respect to the first magnet system (1) relative to a symmetry plane (P) located between the first magnet system (1) and the second magnet system (2), creating an annular plasma confinement area (206) at the symmetry plane (P) with a magnetic field normal to the symmetry plane (P) at the symmetry plane (P).

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.

A system for performing enhanced dense plasma acceleration includes two dense plasma fusion accelerators, each having two electrodes. One of the electrodes is positioned within a volume of the other. A conductive ring couples electrodes of the two plasma fusion accelerators. A plasma sheath from one accelerator and a plasma sheath from the other accelerator interact to form a portion of a cusp pinch. The plasma sheaths form portions of the cusp pinch via apertures of electrodes.

A system for performing enhanced dense plasma acceleration includes two dense plasma fusion accelerators, each having two electrodes. One of the electrodes is positioned within a volume of the other. A conductive ring couples electrodes of the two plasma fusion accelerators. A plasma sheath from one accelerator and a plasma sheath from the other accelerator interact to form a portion of a cusp pinch. The plasma sheaths form portions of the cusp pinch via apertures of electrodes.

A plasma confinement apparatus having a vacuum tight container configured to maintain the pressure of confined plasma; an arrangement of magnet coils inside the vacuum container that define a quasi-spherical polyhedral surface; an arrangement of energetic particle beam injectors mounted inside the vacuum container and outside the magnet coils; an arrangement of energy converters configured to recover net energy produced by fusion reactions within the confined plasma; wherein, a region of quasi-spherical, low-magnetic field intensity is formed inside the arrangement of magnet coils that is configured to confine an plasma within the quasi-spherical polyhedral surface. The arrangement of magnet coils facilitates classical, magnetic confinement of plasma particles for both neutronic and aneutronic reactions, in a scalable, quasi-spherical polyhedral geometry. A quasi-spherical region of low magnetic field intensity formed within the arrangement of magnet coils allows the plasma to be high magnetic beta, thus minimizing Bremsstrahlung-based energy losses.

A plasma confinement apparatus having a vacuum tight container configured to maintain the pressure of confined plasma; an arrangement of magnet coils inside the vacuum container that define a quasi-spherical polyhedral surface; an arrangement of energetic particle beam injectors mounted inside the vacuum container and outside the magnet coils; an arrangement of energy converters configured to recover net energy produced by fusion reactions within the confined plasma; wherein, a region of quasi-spherical, low-magnetic field intensity is formed inside the arrangement of magnet coils that is configured to confine an plasma within the quasi-spherical polyhedral surface. The arrangement of magnet coils facilitates classical, magnetic confinement of plasma particles for both neutronic and aneutronic reactions, in a scalable, quasi-spherical polyhedral geometry. A quasi-spherical region of low magnetic field intensity formed within the arrangement of magnet coils allows the plasma to be high magnetic beta, thus minimizing Bremsstrahlung-based energy losses.

A segment of a field coil, a toroidal field coil, and a method of manufacturing is provided. The segment of a field coil is for use in a superconducting electromagnet. The segment includes an assembly for carrying electrical current in a coil of a magnet. The assembly includes a pre-formed housing comprising a channel configured to retain high temperature superconductor (HTS) tape, the channel including at least one pre-formed curved section. The assembly further includes a plurality of layers of HTS tape fixed within the channel. Wherein the pre-formed curved section has a radius of curvature which is less than a total thickness of the layers of HTS tape in that section divided by twice a maximum permitted strain of the HTS tape.

A nuclear fusion reactor includes a chamber containing plasma and two or more devices which include superconducting electromagnetic coils. At least one of the two or more devices may be biased to a high voltage to provide thermal energy to ions in the magnetic confinement region. In some examples, the chamber and the two or more devices can be coaxial and toroid shaped. In some examples, the chamber can be spherical or cylindrical with the two or more devices being toroid or elongated toroid shaped and formed on opposite faces of a cuboid. The two or more devices may be disposed in the chamber to provide a high-beta magnetic confinement region for the plasma.

A nuclear fusion reactor includes a chamber containing plasma and two or more devices which include superconducting electromagnetic coils. At least one of the two or more devices may be biased to a high voltage to provide thermal energy to ions in the magnetic confinement region. In some examples, the chamber and the two or more devices can be coaxial and toroid shaped. In some examples, the chamber can be spherical or cylindrical with the two or more devices being toroid or elongated toroid shaped and formed on opposite faces of a cuboid. The two or more devices may be disposed in the chamber to provide a high-beta magnetic confinement region for the plasma.