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 multi-scaled capture type vacuum pumping.

The present invention relates to an inertial electrostatic confinement fusion apparatus for electron injection neutralization, which includes a cathode spherical net, an anode, a cathode high-voltage introduction supporting rod, an electron gun for high-energy electron injection, a vacuum system and a high-voltage power supply system. Neutralizing electrons are injected by the electron gun for the high-energy electron injection and an inner electron gun for electron injection in the spherical net into the spherical net and between the spherical net and the anode of the inertial electrostatic confinement fusion apparatus, thereby reducing or eliminating a space charge force generated by deuterium ions, and increasing the deuterium ion density in the spherical net, so that neutron yield and a profit-loss ratio can be increased.

The present invention relates to an inertial electrostatic confinement fusion apparatus for electron injection neutralization, which includes a cathode spherical net, an anode, a cathode high-voltage introduction supporting rod, an electron gun for high-energy electron injection, a vacuum system and a high-voltage power supply system. Neutralizing electrons are injected by the electron gun for the high-energy electron injection and an inner electron gun for electron injection in the spherical net into the spherical net and between the spherical net and the anode of the inertial electrostatic confinement fusion apparatus, thereby reducing or eliminating a space charge force generated by deuterium ions, and increasing the deuterium ion density in the spherical net, so that neutron yield and a profit-loss ratio can be increased.

A compact, simpler, more economical ICF target chamber and reactor design that maintains a low internal pressure, sub-atmospheric, and very small neutron flux on any pressure bearing vessel or steam generating mechanism. The present invention reduces radiant target emission towards the nearest wall of the hohlraum wall and/or sleeve material so that the radiation from target burn exits the end of the hohlraum through a wall material sufficiently thick to contain the target drive radiation, but becomes transparent to the target emitted radiation. The compact converter contains the energy released by the ICF target and converts it into usable heat to create steam. It also converts the excess neutrons, from the ICF target, into tritium. This is then collected with the unburnt fuel tritium.

A compact, simpler, more economical ICF target chamber and reactor design that maintains a low internal pressure, sub-atmospheric, and very small neutron flux on any pressure bearing vessel or steam generating mechanism. The present invention reduces radiant target emission towards the nearest wall of the hohlraum wall and/or sleeve material so that the radiation from target burn exits the end of the hohlraum through a wall material sufficiently thick to contain the target drive radiation, but becomes transparent to the target emitted radiation. The compact converter contains the energy released by the ICF target and converts it into usable heat to create steam. It also converts the excess neutrons, from the ICF target, into tritium. This is then collected with the unburnt fuel tritium.

An assembly for adjusting gas flow patterns and gas-plasma interactions including a toroidal plasma chamber. The toroidal plasma chamber has an injection member, an output member, a first side member and a second side member that are all connected. The first side member has a first inner cross-sectional area in at least a portion of the first side member and a second inner cross-sectional area in at least another portion of the first side member, where the first inner cross-sectional area and the second inner-cross-sectional area being different. The second side member has a third inner cross-sectional area in at least a portion of the second side member and a fourth inner cross-sectional area in at least another portion of the second side member, where the third inner cross-sectional area and the fourth inner-cross-sectional area being different.

An assembly for adjusting gas flow patterns and gas-plasma interactions including a toroidal plasma chamber. The toroidal plasma chamber has an injection member, an output member, a first side member and a second side member that are all connected. The first side member has a first inner cross-sectional area in at least a portion of the first side member and a second inner cross-sectional area in at least another portion of the first side member, where the first inner cross-sectional area and the second inner-cross-sectional area being different. The second side member has a third inner cross-sectional area in at least a portion of the second side member and a fourth inner cross-sectional area in at least another portion of the second side member, where the third inner cross-sectional area and the fourth inner-cross-sectional area being different.

A toroidal field coil for generating a toroidal magnetic field in a nuclear fusion reactor comprising a toroidal plasma chamber having a central column. The toroidal field coil comprises a portion passing through the central column. The portion passing through the central chamber comprises: a low temperature superconductor, LTS, layer (21) formed from LTS; a high temperature superconductor, HTS, layer (22) formed from HTS and located radially outward of the LTS layer. a non-superconducting conductive layer (23) formed from electrically conducting, non-superconducting material and located radially outward of the HTS and LTS layers.

A nuclear fusion reactor includes a geodesic-shaped reaction chamber having at least j planar faces, where j equals 2, 6, 8, 12 or 20 and j conical plasma injectors (CPIs) for creating circular rings of neutral plasma. Each CPI includes a conical inner cathode electrode disposed coaxially within a hollow conical outer anode electrode, the space between the anode electrode and the cathode electrode forming a converging conical plasma channel for creating circular rings of neutral plasma, the converging conical plasma channel accelerating the plasma fuel into a converging plasma ring that comes to a focus at the center of the reaction chamber. The angle between axes of adjacent CPIs defines a CPI face angle, the angle defined by the converging conical plasma channel at its apex defining a CPI convergence angle, wherein the CPI convergence angle is approximately half the CPI face angle.

A nuclear fusion reactor includes a geodesic-shaped reaction chamber having at least j planar faces, where j equals 2, 6, 8, 12 or 20 and j conical plasma injectors (CPIs) for creating circular rings of neutral plasma. Each CPI includes a conical inner cathode electrode disposed coaxially within a hollow conical outer anode electrode, the space between the anode electrode and the cathode electrode forming a converging conical plasma channel for creating circular rings of neutral plasma, the converging conical plasma channel accelerating the plasma fuel into a converging plasma ring that comes to a focus at the center of the reaction chamber. The angle between axes of adjacent CPIs defines a CPI face angle, the angle defined by the converging conical plasma channel at its apex defining a CPI convergence angle, wherein the CPI convergence angle is approximately half the CPI face angle.