A controlled nuclear fusion system includes a vacuum chamber, an electrode cage shaped in a first closed-loop tube in the vacuum chamber, wherein the electrode cage comprises electrically conductive wires configured to confine ions and electrons in the electrode cage and a toroidal electromagnetic coil coiled around outside of the electrode cage and configured to produce a closed-loop magnetic flux in the electrode cage.

A controlled nuclear fusion system includes a vacuum chamber, an electrode cage shaped in a first closed-loop tube in the vacuum chamber, wherein the electrode cage comprises electrically conductive wires configured to confine ions and electrons in the electrode cage and a toroidal electromagnetic coil coiled around outside of the electrode cage and configured to produce a closed-loop magnetic flux in the electrode cage.

A controlled fusion process is provided that can produce a sustained series of fusion reactions: a process that (i) uses a substantially higher reactant density of the deuterium and tritium gases by converging cationic reactants into the higher reaction density at a target cathode rather than relying on random collisions, the converging producing a substantially higher rate of fusion and energy production; (ii) uses a substantially lower input of energy to initiate the fusion; (iii) can be cycled at a substantially higher cycle frequency; (iv) has a practical heat exchange method; (v) is substantially less costly to manufacture, operate, and maintain; and, (vi) has a substantially improved reaction efficiency as a result of not mixing reactants with products.

A controlled fusion process is provided that can produce a sustained series of fusion reactions: a process that (i) uses a substantially higher reactant density of the deuterium and tritium gases by converging cationic reactants into the higher reaction density at a target cathode rather than relying on random collisions, the converging producing a substantially higher rate of fusion and energy production; (ii) uses a substantially lower input of energy to initiate the fusion; (iii) can be cycled at a substantially higher cycle frequency; (iv) has a practical heat exchange method; (v) is substantially less costly to manufacture, operate, and maintain; and, (vi) has a substantially improved reaction efficiency as a result of not mixing reactants with products.

A seal for a vacuum chamber is formed from two outer insulation blocks, an intermediate insulation block, some interior insulation sheets and some exterior insulation sheets. A first outer insulation block seals between a first wall of the vacuum chamber and a first power transmission plate. A second outer insulation block seals between a second wall of the vacuum chamber and a second power transmission plate. The intermediate insulation block seals between the first and second power transmission plates. The interior insulation sheets are arranged in slots in a first side of the intermediate insulation block. The exterior insulation sheets are arranged in the slots in a second side of the intermediate insulation block.

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 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.

Systems and methods are provided that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma chamber. The systems and methods exploit an axially unstable equilibria of the FRC plasma to enforce radial stability, while stabilizing or controlling the axial instability. The systems and methods provide feedback control of the FRC plasma axial position independent of the stability properties of the plasma equilibrium by acting on the voltages applied to a set of external coils concentric with the plasma and using a non-linear control technique.

Systems and methods are provided that facilitate stability of an FRC plasma in both radial and axial directions and axial position control of an FRC plasma along the symmetry axis of an FRC plasma chamber. The systems and methods exploit an axially unstable equilibria of the FRC plasma to enforce radial stability, while stabilizing or controlling the axial instability. The systems and methods provide feedback control of the FRC plasma axial position independent of the stability properties of the plasma equilibrium by acting on the voltages applied to a set of external coils concentric with the plasma and using a non-linear control technique.