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.

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.

A system for reducing plasma instability is disclosed. The system includes: an outer electrode having a first end and a second end spaced from the first end; and an inner electrode disposed inside of a void defined within the outer electrode and arranged coaxial with the outer electrode. The inner electrode includes: a base end defined by the first end of the outer electrode; and an apical end spaced from the base end. The system includes a fiber injector configured to inject a frozen fiber into the void from the apical end of the inner electrode; an electrode power source configured to energize the outer electrode and the inner electrode, and thereby, cause a plasma contained within the outer electrode to flow axially along the frozen fiber; and a frozen fiber power source configured to drive an electrical pulse to the frozen fiber.

A system for reducing plasma instability is disclosed. The system includes: an outer electrode having a first end and a second end spaced from the first end; and an inner electrode disposed inside of a void defined within the outer electrode and arranged coaxial with the outer electrode. The inner electrode includes: a base end defined by the first end of the outer electrode; and an apical end spaced from the base end. The system includes a fiber injector configured to inject a frozen fiber into the void from the apical end of the inner electrode; an electrode power source configured to energize the outer electrode and the inner electrode, and thereby, cause a plasma contained within the outer electrode to flow axially along the frozen fiber; and a frozen fiber power source configured to drive an electrical pulse to the frozen fiber.

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 fusion drive magnetically confining a plasma in a stable plectonemic minimum-energy Taylor states formed from the merging of a plurality of plectonemic Taylor states. Magnetic reconnection converts magnetic energy into ion heating to attain high temperatures before compression. The plasma configuration is then compressed to net gain in a peristaltic magnetic nozzle arrangement. The fusion drive supports generation of electrical power with inductive direct electric or thermal conversion methods.

A fusion drive magnetically confining a plasma in a stable plectonemic minimum-energy Taylor states formed from the merging of a plurality of plectonemic Taylor states. Magnetic reconnection converts magnetic energy into ion heating to attain high temperatures before compression. The plasma configuration is then compressed to net gain in a peristaltic magnetic nozzle arrangement. The fusion drive supports generation of electrical power with inductive direct electric or thermal conversion methods.

A divertor for system supporting high-energy plasma for fusion employs permanent magnets providing far weaker magnetic field strength than conventionally used in cryogenic magnetic systems through an ability to place the permanent magnets in close proximity to the plasma containment volume.

A divertor for system supporting high-energy plasma for fusion employs permanent magnets providing far weaker magnetic field strength than conventionally used in cryogenic magnetic systems through an ability to place the permanent magnets in close proximity to the plasma containment volume.