Examples of advanced fuel cycles for fusion reactors are described. Examples include fuel cycles for use in field reverse configuration (FRC) plasma reactors. In some examples, reaction gases may be removed from a fusion reactor between pulses (e.g. plasmoid collisions). In some examples, a D-.sup.3He reaction is performed, with the .sup.3He provided from decay of byproducts of previous reactions (e.g. tritium).

A superconducting magnet for producing part of a substantially toroidal field in a device is described. The magnet comprises: a set of conductors comprising one or more first conductors (31f) and one or more second conductors (32f), and a set of joints (33). Each of the joints (33) connects a region of a first conductor (31f) with a region of a second conductor (32f) to form a series of alternating first and second conductors corresponding to at least part of a winding of the magnet. Each of the joints (33) is positioned away from a midplane of the toroidal field. The joints (33) are positioned on alternating sides of the midplane. Each first conductor (3 If) passes through the midplane at a smaller distance from an axis of rotation of the toroidal field than does each second conductor (32f). Each of the regions is elongate and extends in a direction at least partly away from the midplane.

A superconducting magnet for producing part of a substantially toroidal field in a device is described. The magnet comprises: a set of conductors comprising one or more first conductors (31f) and one or more second conductors (32f), and a set of joints (33). Each of the joints (33) connects a region of a first conductor (31f) with a region of a second conductor (32f) to form a series of alternating first and second conductors corresponding to at least part of a winding of the magnet. Each of the joints (33) is positioned away from a midplane of the toroidal field. The joints (33) are positioned on alternating sides of the midplane. Each first conductor (3 If) passes through the midplane at a smaller distance from an axis of rotation of the toroidal field than does each second conductor (32f). Each of the regions is elongate and extends in a direction at least partly away from the midplane.

A plasma confinement system includes an enclosure, one or more internal magnetic coils suspended within the enclosure in a plasma region, and one or more supports configured to support the one or more internal magnetic coils suspended within the enclosure. Each support of the one or more supports includes a first end and a second end opposite the first end. The first end is coupled to an interior portion of the enclosure and the second end is coupled to a component disposed within the plasma region. Each support further includes electrical conducting material disposed between the first end and the second end. The electrical conducting material is configured to, when supplied with one or more electrical currents, generate a magnetic field having a magnetic field gradient that varies along the support from the first end to the second end.

The fusion reactor of the invention comprises a plurality of elongated triangular electrodes aligned in a cylindrical shape to form an axially symmetric containment geometry. The electrodes are separated by means of electrical insulator preferably pure swept Quartz (SiO2). The Triangular electrodes, are made out of very high electro conductive, high strength, heat resistant, radiation resistant and neutrons moderating material such as thorium carbide, uranium carbide or silicon carbide or the like which is preferably made by ceramic powder metallurgy process. Each electrode includes a cooling structure or flow channel formed in the internal structure allowing for a cooling fluid for extracting heat caused by plasma and nuclear reactions. The acceleration channels electrodes of the fusion reactor are of triangular shape and are protected with a continuously changing protective film or layer of high electro-conductive fissile or fertile material such as thorium carbide or uranium carbide. Lithium may be added for the reactor to breed its own Tritium.

The fusion reactor of the invention comprises a plurality of elongated triangular electrodes aligned in a cylindrical shape to form an axially symmetric containment geometry. The electrodes are separated by means of electrical insulator preferably pure swept Quartz (SiO2). The Triangular electrodes, are made out of very high electro conductive, high strength, heat resistant, radiation resistant and neutrons moderating material such as thorium carbide, uranium carbide or silicon carbide or the like which is preferably made by ceramic powder metallurgy process. Each electrode includes a cooling structure or flow channel formed in the internal structure allowing for a cooling fluid for extracting heat caused by plasma and nuclear reactions. The acceleration channels electrodes of the fusion reactor are of triangular shape and are protected with a continuously changing protective film or layer of high electro-conductive fissile or fertile material such as thorium carbide or uranium carbide. Lithium may be added for the reactor to breed its own Tritium.

The invention relates to a method for eliminating neutrons from fission, fusion or aneutronic nuclear reactions in a reactor, in particular in a laser-driven nuclear fusion reactor which operates with hydrogen and the boron-11 isotope, in which method at least some moderated neutrons are made to undergo a nuclear reaction with tin. As a result of the nuclear reactions with tin, the neutrons convert the tin nuclei into stable nuclei having a higher atomic weight resulting from neutron capture. The invention also relates to a reactor which is designed for energy conversion by means of fission, fusion or aneutronic nuclear reactions and for generating electric energy, wherein the reactor contains a neutron elimination device which contains tin and is arranged such that at least some moderated neutrons are made to undergo a nuclear reaction with the tin.

The invention relates to a method for eliminating neutrons from fission, fusion or aneutronic nuclear reactions in a reactor, in particular in a laser-driven nuclear fusion reactor which operates with hydrogen and the boron-11 isotope, in which method at least some moderated neutrons are made to undergo a nuclear reaction with tin. As a result of the nuclear reactions with tin, the neutrons convert the tin nuclei into stable nuclei having a higher atomic weight resulting from neutron capture. The invention also relates to a reactor which is designed for energy conversion by means of fission, fusion or aneutronic nuclear reactions and for generating electric energy, wherein the reactor contains a neutron elimination device which contains tin and is arranged such that at least some moderated neutrons are made to undergo a nuclear reaction with the tin.

Methods and systems are provided for plasma confinement utilizing various electrode and valve configurations. In one example, a device includes a first electrode positioned to define an outer boundary of an acceleration volume, a second electrode arranged coaxially with respect to the first electrode and positioned to define an inner boundary of the acceleration volume, at least one power supply to drive an electric current along a Z-pinch plasma column between the first second electrodes, and a set of valves to provide gas to the acceleration volume to fuel the Z-pinch plasma column, wherein an electron flow of the electric current is in a first direction from the second electrode to the first electrode. In additional or alternative examples, a shaping part is conductively connected to the second electrode to, in a presence of the gas, cause a gas breakdown of the gas to generate a sheared flow velocity profile.

Systems and methods that facilitate forming and maintaining FRCs with superior stability as well as particle, energy and flux confinement and, more particularly, systems and methods that facilitate forming and maintaining FRCs with elevated system energies and improved sustainment utilizing neutral beam injection and high harmonic fast wave electron heating.