According to various embodiments, an FRC fusion reactor is disclosed. The FRC fusion reactor includes a main chamber containing an FRC core and an energy and ash removal shell (EARS). The FRC fusion reactor further includes at least one divertor chamber connected to the main chamber via a divertor throat. The divertor chamber includes a plasma extruder positioned on a major axis of the FRC fusion reactor and a controllable distance along the major axis from the divertor throat. The plasma extruder has a diameter approximately ½ a diameter of the divertor throat and is configured to block plasma flow towards the FRC core to create a gap region between the FRC core and the EARS.

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.

Disclosed herein is a stellarator comprising two sets of coils, namely a set of encircling coils which encircle the plasma axis, and a set of shaping coils which do not encircle any other coil or the plasma. In some embodiments, the encircling coils include a structural element to maintain their shape under magnetic forces. In some embodiments, the shaping coils are mounted onto one or more structural elements which, together with the shaping coils, constitute a field shaping unit. Also disclosed is a controller which may modify the electrical current flowing in one or more subsets of the coils in order to achieve target plasma parameters. Also disclosed is a method of designing a set of shaping coils by discretizing a surface dipole or current potential distribution.

Methods, apparatuses, devices, and systems for creating, controlling, conducting, and optimizing fusion activities of nuclei. The controlled fusion activities cover a spectrum of reactions from aneutronic, fusion reactions that produce essentially no neutrons, to neutronic, fusion reactions that produce substantial numbers of neutrons.

Methods, apparatuses, devices, and systems for creating, controlling, conducting, and optimizing fusion activities of nuclei. The controlled fusion activities cover a spectrum of reactions from aneutronic, fusion reactions that produce essentially no neutrons, to neutronic, fusion reactions that produce substantial numbers of neutrons.

A tokamak plasma vessel. The tokamak plasma vessel comprises a toroidal plasma chamber, a plurality of poloidal field coils, an upper divertor assembly, and a lower divertor assembly. The plurality of poloidal field coils are configured to provide a poloidal magnetic field having a substantially symmetric plasma core and an upper and lower null, such that ions in a scrape off layer outside the plasma core are directed by the magnetic field past one of the upper and lower nulls to divertor surfaces of the respective upper and lower divertor assembly. Each of the upper and lower divertor assembly comprises a liquid metal inlet and a liquid metal outlet located below the liquid metal inlet. Each of the upper and lower divertor assembly is configured such that in use liquid metal flows from the liquid metal inlet to the liquid metal outlet over at least one divertor surface of the divertor assembly.

A tokamak plasma vessel. The tokamak plasma vessel comprises a toroidal plasma chamber, a plurality of poloidal field coils, an upper divertor assembly, and a lower divertor assembly. The plurality of poloidal field coils are configured to provide a poloidal magnetic field having a substantially symmetric plasma core and an upper and lower null, such that ions in a scrape off layer outside the plasma core are directed by the magnetic field past one of the upper and lower nulls to divertor surfaces of the respective upper and lower divertor assembly. Each of the upper and lower divertor assembly comprises a liquid metal inlet and a liquid metal outlet located below the liquid metal inlet. Each of the upper and lower divertor assembly is configured such that in use liquid metal flows from the liquid metal inlet to the liquid metal outlet over at least one divertor surface of the divertor assembly.

Methods, apparatuses, devices, and systems for creating, controlling, conducting, and optimizing fusion activities of nuclei. The controlled fusion activities cover a spectrum of reactions from aneutronic, fusion reactions that produce essentially no neutrons, to neutronic, fusion reactions that produce substantial numbers of neutrons.

Methods, apparatuses, devices, and systems for creating, controlling, conducting, and optimizing fusion activities of nuclei. The controlled fusion activities cover a spectrum of reactions from aneutronic, fusion reactions that produce essentially no neutrons, to neutronic, fusion reactions that produce substantial numbers of neutrons.