A device and method for generating plasma conditions for deuterium-tritium and advanced fuel thermonuclear fusion consisting of an inner helicity-containing plasma such as a spheromak compact toroid bounded by a plurality of outer cusped magnetic fields. Helicity driven by steady-inductive helicity injectors energizes the plasmoid with helicity. The device further includes means for driving fluid rotation about the device axis, about the device magnetic axis, and means for a hot electron sheath. Means are also provided for reducing particle losses out through the open cusp field lines through helicity injector rectification.

A method and apparatus for forming torsional magnetic reconnection, and converting stored magnetic energy into charged particle kinetic energy and particle acceleration, is claimed. A torsional magnetic reconnection apparatus generally comprises (1) a vacuum environment housing (2) a plurality of conducting coils to form a magnetic field fan-spine topology and (3) a plasma generation device providing an azimuthal magnetic field perturbation such that current sheets are formed and magnetic reconnection processes can occur. Electric current energization of the plurality of conducting coils generates a potential magnetic fan-spine topology. A simultaneous capacitor bank discharge forms and axially drives a plasma sheath, featuring an azimuthal magnetic field, toward the fan-spine magnetic null that forces the diffusion of magnetic flux through the plasma. This magnetic to plasma kinetic energy conversion process accelerates charged particles far away from the reconnection region along open magnetic field lines.

Systems and methods to reduce the amplitude of undesirable eddy currents in conducting structures, e.g., induced by the translation of an FRC into a confinement chamber, while leaving beneficial eddy currents unaffected. This is achieved by inducing opposing currents in the same conducting structures prior to plasma translation into the confinement chamber.

Systems and methods to reduce the amplitude of undesirable eddy currents in conducting structures, e.g., induced by the translation of an FRC into a confinement chamber, while leaving beneficial eddy currents unaffected. This is achieved by inducing opposing currents in the same conducting structures prior to plasma translation into the confinement chamber.

A high performance field reversed configuration (FRC) system includes a central confinement vessel, two diametrically opposed reversed-field-theta-pinch formation sections coupled to the vessel, and two divertor chambers coupled to the formation sections. A magnetic system includes quasi-dc coils axially positioned along the FRC system components, quasi-dc mirror coils between the confinement chamber and the formation sections, and mirror plugs between the formation sections and the divertors. The formation sections include modular pulsed power formation systems enabling static and dynamic formation and acceleration of the FRCs. The FRC system further includes neutral atom beam injectors, pellet injectors, gettering systems, axial plasma guns and flux surface biasing electrodes. The beam injectors are preferably angled toward the midplane of the chamber. In operation, FRC plasma parameters including plasma thermal energy, total particle numbers, radius and trapped magnetic flux, are sustainable at or about a constant value without decay during neutral beam injection.

A high performance field reversed configuration (FRC) system includes a central confinement vessel, two diametrically opposed reversed-field-theta-pinch formation sections coupled to the vessel, and two divertor chambers coupled to the formation sections. A magnetic system includes quasi-dc coils axially positioned along the FRC system components, quasi-dc mirror coils between the confinement chamber and the formation sections, and mirror plugs between the formation sections and the divertors. The formation sections include modular pulsed power formation systems enabling static and dynamic formation and acceleration of the FRCs. The FRC system further includes neutral atom beam injectors, pellet injectors, gettering systems, axial plasma guns and flux surface biasing electrodes. The beam injectors are preferably angled toward the midplane of the chamber. In operation, FRC plasma parameters including plasma thermal energy, total particle numbers, radius and trapped magnetic flux, are sustainable at or about a constant value without decay during neutral beam injection.

Methods, apparatuses, devices, and systems for producing and controlling and fusion activities of nuclei. Hydrogen atoms or other neutral species (neutrals) are induced to rotational motion in a confinement region as a result of ion-neutral coupling, in which ions are driven by electric and magnetic fields. The controlled fusion activities cover a spectrum of reactions including aneutronic reactions such as proton-boron-11 fusion reactions.

Methods, apparatuses, devices, and systems for producing and controlling and fusion activities of nuclei. Hydrogen atoms or other neutral species (neutrals) are induced to rotational motion in a confinement region as a result of ion-neutral coupling, in which ions are driven by electric and magnetic fields. The controlled fusion activities cover a spectrum of reactions including aneutronic reactions such as proton-boron-11 fusion reactions.

A high performance field reversed configuration (FRC) system includes a central confinement vessel, two diametrically opposed reversed-field-theta-pinch formation sections coupled to the vessel, and two divertor chambers coupled to the formation sections. A magnetic system includes quasi-dc coils axially positioned along the FRC system components, quasi-dc mirror coils between the confinement chamber and the formation sections, and mirror plugs between the formation sections and the divertors. The formation sections include modular pulsed power formation systems enabling static and dynamic formation and acceleration of the FRCs. The FRC system further includes neutral atom beam injectors, pellet injectors, gettering systems, axial plasma guns and flux surface biasing electrodes. The beam injectors are preferably angled toward the midplane of the chamber. In operation, FRC plasma parameters including plasma thermal energy, total particle numbers, radius and trapped magnetic flux, are sustainable at or about a constant value without decay during neutral beam injection.

A high performance field reversed configuration (FRC) system includes a central confinement vessel, two diametrically opposed reversed-field-theta-pinch formation sections coupled to the vessel, and two divertor chambers coupled to the formation sections. A magnetic system includes quasi-dc coils axially positioned along the FRC system components, quasi-dc mirror coils between the confinement chamber and the formation sections, and mirror plugs between the formation sections and the divertors. The formation sections include modular pulsed power formation systems enabling static and dynamic formation and acceleration of the FRCs. The FRC system further includes neutral atom beam injectors, pellet injectors, gettering systems, axial plasma guns and flux surface biasing electrodes. The beam injectors are preferably angled toward the midplane of the chamber. In operation, FRC plasma parameters including plasma thermal energy, total particle numbers, radius and trapped magnetic flux, are sustainable at or about a constant value without decay during neutral beam injection.