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.

Systems and methods utilizing successive, axially symmetric acceleration and adiabatic compression stages to heat and accelerate two compact tori towards each other and ultimately collide and compress the compact tori within a central chamber. Alternatively, systems and methods utilizing successive, axially asymmetric acceleration and adiabatic compression stages to heat and accelerate a first compact toroid towards and position within a central chamber and to heat and accelerate a second compact toroid towards the central chamber and ultimately collide and merge the first and second compact toroids and compress the compact merge tori within the central chamber.

Systems and methods that facilitate non-pertubative measurements of low and null magnetic field in high temperature plasmas.

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 or CT 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.

According to some embodiments, a system for widening and densifying a scrape-off layer (SOL) in a field reversed configuration (FRC) fusion reactor is disclosed. The system includes a gas box at one end of the reactor including a gas inlet system and walls of suitable heat bearing materials. The system further includes an exit orifice adjoining the gas box, wherein the exit orifice has a controllable radius and length to allow plasma to flow out from the gas box to populate the SOL with the plasma. The system may also include fusion products, which decrease in speed in the plasma in the SOL, allowing energy to be extracted and converted into thrust or electrical power and further allowing ash to be extracted to reduce neutron emissions and maintain high, steady-state fusion power.

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 magnetic confinement system includes a magnetic minor device that includes a chamber to hold a target plasma and a coil arrangement to generate a magnetic field configuration in the chamber to confine the target plasma in cylindrically-symmetric form in the chamber, the magnetic field configuration having open ends. The magnetic confinement system further includes plasma guns to generate plasma pistons and project the plasma pistons at the open ends of the magnetic field configuration. In operation, the plasma pistons converge towards each other to close the open ends of the magnetic field configuration and to compress and heat the target plasma.

A combination flux loop and B-dot probe comprising a single mineral insulated cable having an outer sheath of, e.g., stainless steel or the like, and three (3) conductors positioned within the sheath and embedded in a mineral insulator such as, e.g., MgO. One of the conductors forms a flux loop having a single loop and second and third conductors forming a B-dot probe comprises a single wire having a double loop. The combination probe is configured to prevent twisting of the conductors along a curved bend as the combined probe is fashioned into a curved shape. To prevent twisting, the conductors may be formed as ribbon wires having a generally flat, rectangular shaped cross-section and/or the sheath may have a generally oval or rectangular shaped cross-section.

According to some embodiments, a system for widening and densifying a scrape-off layer (SOL) in a field reversed configuration (FRC) fusion reactor is disclosed. The system includes a gas box at one end of the reactor including a gas inlet system and walls of suitable heat bearing materials. The system further includes an exit orifice adjoining the gas box, wherein the exit orifice has a controllable radius and length to allow plasma to flow out from the gas box to populate the SOL with the plasma. The system may also include fusion products, which decrease in speed in the plasma in the SOL, allowing energy to be extracted and converted into thrust or electrical power and further allowing ash to be extracted to reduce neutron emissions and maintain high, steady-state fusion power.

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 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.