Abstract: Systems, devices, and methods for generating an orbital confinement fusion reaction are described. An orbital confinement fusion device can include a cathodic inner electrode defining a longitudinal axis of the device. The inner electrode can include an emitter material. The orbital confinement fusion device can include an anodic outer electrode, concentric with the longitudinal axis and defining a chamber between the inner electrode and the outer electrode. The orbital confinement fusion device can also include a plurality of magnetic field generators disposed in a coaxial arrangement relative to the longitudinal axis. The plurality of magnetic field generators can be configured to form a magnetic field parallel to the longitudinal axis in the chamber.

Abstract: A divertor for system supporting plasma for fusion employs permanent magnets providing far weaker magnetic field strength than conventionally used in cryogenic magnetic systems through an ability to place the permanent magnets in close proximity to the plasma containment volume.

Abstract: 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 lay 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.

Abstract: An architecture for an inertial confinement fusion system is disclosed. The system includes a fusion chamber for producing neutrons from a fusion reaction, and a laser system in which lasers are arranged about a vacuum chamber to provide energy to the fusion chamber to initiate the fusion reaction. The beam paths between the lasers and the fusion chamber are configured to prevent neutrons from the fusion chamber from reaching the laser system at a level that would preclude human access to the laser system.

Abstract: 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.

Abstract: 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.

Abstract: A high temperature superconducting, HTS, field coil. The HTS field coil comprises a plurality of turns and a partially insulating layer. The plurality of turns comprises HTS material and metallic stabilizer. The partially insulating layer separates the turns, such that current can be shared between turns via the partially insulating layer. The partially insulating layer comprises an electrically conducting layer, and first and second insulating layers. The electrically conducting layer is coated on one side with the first insulating layer and on the other side with the second insulating layer. Each insulating layer has one or more windows through which electrical contact can be made between the turns and the electrically conducting layer. The windows in the first insulating layer are offset in the plane of the electrically conducting strip from the windows in the second insulating layer.

Abstract: There is disclosed a toroidal field coil for use in a spherical tokamak. The toroidal field coil comprises a central column and a plurality of return limbs. The central column comprises a plurality of exfoliated HTS tapes, and the return limbs comprise a plurality of substrated HTS tapes. Each exfoliated HTS tape comprises a ReBCO layer bonded to respective metal interface layers on each side of the ReBCO layer, each metal interface layer being bonded to a metal stabiliser layer. Each substrated HTS tape comprises a ReBCO layer bonded on one side to a metal interface layer and on the other side to an oxide buffer stack, the metal interface layer being bonded to a metal stabiliser layer and the oxide buffer stack being bonded to a substrate.

Abstract: 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.

Abstract: 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.

Abstract: A toroidal field coil for generating a toroidal magnetic field in a nuclear fusion reactor includes a toroidal plasma chamber having a central column. The toroidal field coil has a plurality of windings configured to pass through the central column and around the outside of the plasma chamber. Each winding includes a cable having a plurality of stacked high temperature superconductor (HTS) tapes, each HTS tape including one or more layers of a high temperature superconductor material. With the toroidal field coil in place in the reactor, a face of each HTS tape is substantially perpendicular to a direction of maximal neutron flux during reactor operation as the cable passes through the center column.

Abstract: 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.

Abstract: Systems and methods are discussed to create radiation from one or more compact toroids. Compact toroids can be created from plasma of gases within a confinement chamber using a plurality of coils of various densities of windings. High current pulses can be generated within the coil and switched at high frequencies to repeatedly generate compact toroids within the plasma. The plasma can produce radiation at various wavelengths that is focused toward a target or an intermediate focus.

Abstract: Embodiments of systems and methods for compressing plasma are described in which plasma pressures above the breaking point of solid material can be achieved by injecting a plasma into a funnel of liquid metal in which the plasma is compressed and/or heated.

Abstract: A plasma confinement system is provided that includes a confinement chamber that includes one or more enclosures of respective helicity injectors. The one or more enclosures are coupled to ports at an outer radius of the confinement chamber. The system further includes one or more conductive coils aligned substantially parallel to the one or more enclosures and a further set of one or more conductive coils respectively surrounding portions of the one or more enclosures. Currents may be provided to the sets of conductive coils to energize a gas within the confinement chamber into a plasma. Further, a heat-exchange system is provided that includes an inner wall, an intermediate wall, an outer wall, and pipe sections configured to carry coolant through cavities formed by the walls.

Abstract: Systems and methods are discussed to create radiation from one or more compact toroids. Compact toroids can be created from plasma of gases within a confinement chamber using a plurality of coils of various densities of windings. High current pulses can be generated within the coil and switched at high frequencies to repeatedly generate compact toroids within the plasma. The plasma can produce radiation at various wavelengths that is focused toward a target or an intermediate focus.

Abstract: A method, system, and apparatus are disclosed for liquid lithium first walls for electromagnetic control of plasmas in fusion power reactor environments. In particular, the method involves installing at least one layer of at least one tile on the surface area of the internal walls of the reactor chamber. A portion of the tile(s) facing the interior of the reactor chamber includes a plurality of channels. The method further involves applying an electric charge to the liquid lithium. Further, the method involves circulating the liquid lithium throughout the interior network of the tile(s) to allow for the liquid lithium to flow into the channels and to reach the external surface of the tile(s) that faces the interior of the reactor chamber. In some embodiments, the method also involves installing at least one magnetic coil between the tile(s) and the surface area of the internal walls of the reactor chamber.

Abstract: A plasma interaction simulator is presented. The simulator magnetically induces multiple distinct flows of plasma within a physical plasma vessel. The plasma flows collide with each other at flow interaction boundaries where discontinuities arising due to differences between the flows give rise to interactions. Sensors can be incorporated into the plasma simulator to observe and collect data about the plasma flow interactions.

Abstract: Embodiments of systems and methods for compressing plasma are described in which plasma pressures above the breaking point of solid material can be achieved by injecting a plasma into a funnel of liquid metal in which the plasma is compressed and/or heated.

Abstract: A compressor assembly and the method of using the same which includes an elongated spiral passageway within which a compact toroid plasma, such as a compact toroid plasma structure, can be efficiently compressed to a high-energy state by compressing the compact toroid plasma structure by its own momentum against the wall of the spiral passageway in a manner to induce heating by conservation of energy. The compressor assembly also includes a burn chamber that is in communication with the spiral passageway and into which the compressed compact toroid plasma structure is introduced following its compression.

Abstract: Embodiments of systems and methods for compressing plasma are disclosed in which plasma can be compressed by impact of a projectile on a magnetized plasma in a liquid metal cavity. The projectile can melt in the liquid metal cavity, and liquid metal may be recycled to form new projectiles.

Abstract: Embodiments of systems and methods for compressing plasma are disclosed in which plasma can be compressed by impact of a projectile on a magnetized plasma in a liquid metal cavity. The projectile can melt in the liquid metal cavity, and liquid metal may be recycled to form new projectiles.

Abstract: A method of inductively energizing a plasma in a confinement chamber (110) is disclosed. A gas is introduced to the confinement chamber (110) and energized to form a plasma having a toroidal current defined by rotation of the plasma within the confinement chamber (110). Magnetic flux is injected into the confinement chamber (110) by applying current through conductive coils (126) of a helicity injector (120) with ends fluidly connected to the confinement chamber (110). Voltage (122) is applied across the ends of the helicity injector (120) to create edge currents around an outer surface of the plasma in the confinement chamber (110) and asymmetric magnetic perturbations across the plasma sufficient to couple adjacent zonal flows. Magnetic flux (126) is injected and voltage (122) is applied across the helicity injector periodically and in phase at a frequency that exceeds 5.8 kilohertz. Gas is removed from the confinement chamber (110) to achieve a plasma density sufficient for separatrix formation.

Abstract: Embodiments of systems and methods for compressing plasma are described in which plasma pressures above the breaking point of solid material can be achieved by injecting a plasma into a funnel of liquid metal in which the plasma is compressed and/or heated.

Abstract: An efficient compact nuclear fusion reactor for use as a neutron source or energy source is described. The reactor comprises a toroidal plasma chamber and a plasma confinement system arranged to generate a magnetic field for confining a plasma in the chamber. The plasma confinement system is configured so that a major radius of the confined plasma is 1.5 m or less. The reactor is constructed using high temperature superconducting toroidal magnets, which may be operated at low temperature (77K or lower) to provide enhanced performance. The toroidal magnetic field can be increased to 5 T or more giving significant increases in fusion output, so that neutron output is very efficient and the reactor can produce a net output of energy.

Abstract: Embodiments of systems and methods for compressing plasma are described in which plasma pressures above the breaking point of solid material can be achieved by injecting a plasma into a funnel of liquid metal in which the plasma is compressed and/or heated.

Abstract: A compact nuclear fusion reactor for use as a neutron source is described. The reactor comprises a toroidal plasma chamber (34) and a plasma confinement system (31) arranged to generate a magnetic field for confining a plasma in the plasma chamber (34). The plasma confinement system (31) is configured so that a major radius of the confined plasma is 0.75 m or less. The reactor is configure to operate with a plasma current of 2 MA or less. The magnetic field includes a toroidal component of 5 T or less. Despite these low values, the reactor can generate a neutron output of 1 MW or more.

Abstract: A compressor assembly and the method of using the same which includes an elongated spiral passageway within which a compact toroid plasma, such as a compact toroid plasma structure, can be efficiently compressed to a high-energy state by compressing the compact toroid plasma structure by its own momentum against the wall of the spiral passageway in a manner to induce heating by conservation of energy. The compressor assembly also includes a burn chamber that is in communication with the spiral passageway and into which the compressed compact toroid plasma structure is introduced following its compression.

Abstract: A magnetohydrodynamic simulator that includes a plasma container. The magnetohydrodynamic simulator also includes an first ionizable gas substantially contained within the plasma container. In addition, the magnetohydrodynamic simulator also includes a first loop positioned adjacent to the plasma container, wherein the first loop includes a gap, a first electrical connection on a first side of the gap, a second electrical connection of a second side of the gap, and a first material having at least one of low magnetic susceptibility and high conductivity. The first loop can be made up from an assembly of one or a plethora or wire loop coils. In such cases, electrical connection is made through the ends of the coil wires. The magnetohydrodynamic simulator further includes an electrically conductive first coil wound about the plasma container and through the first loop.

Abstract: A magnetohydrodynamic simulator that includes a plasma container. The magnetohydrodynamic simulator also includes an first ionizable gas substantially contained within the plasma container. In addition, the magnetohydrodynamic simulator also includes a first loop positioned adjacent to the plasma container, wherein the first loop includes a gap, a first electrical connection on a first side of the gap, a second electrical connection of a second side of the gap, and a first material having at least one of low magnetic susceptibility and high conductivity. The first loop can be made up from an assembly of one or a plethora or wire loop coils. In such cases, electrical connection is made through the ends of the coil wires. The magnetohydrodynamic simulator further includes an electrically conductive first coil wound about the plasma container and through the first loop.

Abstract: Embodiments of systems and methods for compressing plasma are disclosed in which plasma can be compressed by impact of a projectile on a magnetized plasma in a liquid metal cavity. The projectile can melt in the liquid metal cavity, and liquid metal may be recycled to form new projectiles.

Abstract: Disclosed are reactors, methods, and devices for improved nuclear fusion reactors that provide neutrons with a sufficient power density to efficiently breed fissile nuclear material, which can then optionally be used as an energy source. The reactors can also be used in improved nuclear fuel cycles wherein an adequate supply of fissile nuclear material is provided to nuclear power plants. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: Disclosed is a device comprising a chamber enclosed by walls about a central axis. The chamber has an inner radius and an outer radius relative to the central axis and is configured to magnetically contain a core plasma. The device is further comprised of a divertor plate configured for receiving exhaust heat. The divertor plate has a divertor radius relative to the central axis. The divertor radius is greater than or equal to the sum of a plasma minor radius and a major radius of the peak point closest to the corresponding divertor plate. The device can be used for containing a fusion plasma, as a compact fusion neutron source, or as a compact fusion energy source. Methods of exhausting heat from such a device when plasma is present therein are also described. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: Embodiments of systems and methods for compressing plasma are described in which plasma pressures above the breaking point of solid material can be achieved by injecting a plasma into a funnel of liquid metal in which the plasma is compressed and/or heated.

Abstract: Embodiments of systems and methods for compressing plasma are disclosed in which plasma can be compressed by impact of a projectile on a magnetized plasma in a liquid metal cavity. The projectile can melt in the liquid metal cavity, and liquid metal may be recycled to form new projectiles.

Abstract: Disclosed are a replaceable fusion core that can be inserted and removed from the core of a nuclear fission reactor, thereby enabling the replacement of materials exposed to neutron flux and reducing outage times and “hybrid reactor, method, and device for improved nuclear fusion reactors to provide sufficient flux of fast neutrons with sufficient energy to transmutate transuranic wastes from nuclear fission and to be used in improved nuclear fuel cycles so as to effectively reduce the amount radio-toxicity, and the risks and costs of the disposal of nuclear waste, thereby reducing the cost of nuclear energy and increasing its acceptability as an energy source. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: Disclosed is a device comprising a chamber enclosed by walls about a central axis. The chamber has an inner radius and an outer radius relative to the central axis and is configured to magnetically contain a core plasma. The device is further comprised of a divertor plate configured for receiving exhaust heat. The divertor plate has a divertor radius relative to the central axis. The divertor radius is greater than or equal to the sum of a plasma minor radius and a major radius of the peak point closest to the corresponding divertor plate. The device can be used for containing a fusion plasma, as a compact fusion neutron source, or as a compact fusion energy source. Methods of exhausting heat from such a device when plasma is present therein are also described. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: A method for obtaining high temperature plasma in the Field Reversed Configuration (FRC) magnetic topology is described, allowing for compression, retention and heating plasma, which can be used for obtaining thermonuclear energy or laser pumping. The storage of the magnetic field energy is accomplished by creating a current in the winding of a solenoid over a working volume. In addition, a pulse toroidal magnetic field with force lines perpendicular to the magnetic field of the solenoid is created via the transmission of a current through the working volume. Then, the current is broken off in the solenoid winding when it reaches its maximum to excite a closed current loop in the plasma created in the working volume. The change of the direction of magnetic field outside the current-carrying loop in the plasma is achieved either by changing to the opposite direction of the current in the solenoid or transmitting the current in additional turns parallel to the turns of the solenoid.

Abstract: The invention relates to method and devices for producing stable hot plasma. In particular, the invention can be applied for realizing stable plasma in a thermonuclear reactor to provide energy source for power generation. In the method plasma is confined by pressure of AC magnetic field concentrated in a layer between plasma surface and surrounding conducting shell in which stabilizing feedback on the confined plasma is created by achieving conservation of the AC magnetic flux amplitude. The device for realization of the proposed method comprises a toroidal conducting shell filled with plasma, with AC voltages applied to insulated cuts in the shell made in poloidal and toroidal directions such that said AC magnetic field is created by AC currents in the shell and image currents on the plasma surface.

Abstract: Process for energy production characterized by the generation of a positive concentric pulsating magnetic field by means of magnetic impulses convergent in only one point of the space, such to cause the temporary fusion of nuclei of hydrogen isotopes and their subsequent release; reactor for carrying out the process and apparatus containing said reactors.

Abstract: The invention is a plasma-generating device useful in a wide variety of industrial processes. The plasma is formed in a chamber having a toroidal topology, and is heated inductively. As with all inductive plasmas, a primary coil carries an applied AC current, which, in turn, generates a corresponding applied AC magnetic flux inside the plasma. This flux induces current to flow through the plasma in closed paths that encircle the flux, thereby heating and maintaining the plasma. In this invention, the applied AC current flows through the primary coil around substantially the short poloidal direction on the torus. Accordingly, the applied magnetic flux is caused to circulate through the plasma along the larger toroidal direction. Finally, the current induced within the plasma will flow in the poloidal direction, anti-parallel to the applied primary current.

Abstract: A compound plasma configuration can be formed from a device having pins, and an annular electrode surrounding the pins. A cylindrical conductor is electrically connected to, and coaxial with, the annular electrode, and a helical conductor coaxial with the cylindrical conductor. The helical conductor is composed of wires, each wire electrically connected to each pin. The annular electrode and the pins are disposed in the same direction away from the interior of the conducting cylinder.

Abstract: A novel method and apparatus are described for modifying the field within the toroidal chamber of a stellarator or a tokamak. At least one additional electrical conductor is arranged around the straight axis of the toroidal chamber and has a sawtooth or zigzag shape with the number of teeth being the same as the number of toroidal field coils or a factor thereof. The conductor is shaped so that one edge of each tooth is substantially parallel to a portion of one of the toroidal field coils while the other edge of the tooth extends from the upper portion of one coil to a lower portion of the toroidal field coil associated with another tooth. The conductor is adapted to carry a current that is approximately the same as that in the toroidal field coil but in the opposite direction.

Abstract: The unwanted or unreacted decaborane gas that results from a boronizing operation using decaborane which is solid at ordinary temperatures but which is heated to a gaseous phase for injection into a vacuum vessel is passed through a metal tube packed with the granules of an alkaline oxidizing agent consisting of potassium permanganate and potassium hydroxide, whereby the decaborane gas is oxidized to solid and gaseous stable substances including manganese compounds and hydrogen. This provides an effective method for removing boron from the boron-containing exhaust gases that result from the coating of the inner surfaces of vacuum vessels in nuclear fusion reactors with an evaporated boron film.

Abstract: An apparatus and method of extracting power from energetic ions produced by nuclear fusion in a toroidal plasma to enhance respectively the toroidal plasma current and fusion reactivity. By injecting waves of predetermined frequency and phase traveling substantially in a selected poloidal direction within the plasma, the energetic ions become diffused in energy and space such that the energetic ions lose energy and amplify the waves. The amplified waves are further adapted to travel substantially in a selected toroidal direction to increase preferentially the energy of electrons traveling in one toroidal direction which, in turn, enhances or generates a toroidal plasma current. In an further adaptation, the amplified waves can be made to preferentially increase the energy of fuel ions within the plasma to enhance the fusion reactivity of the fuel ions. The described direct, or in situ, conversion of the energetic ion energy provides an efficient and economical means of delivering power to a fusion reactor.

Abstract: An electron injection scheme for controlling transport in a tokamak plasma. Electrons with predominantly perpendicular energy are injected into a ripple field region created by a group of localized poloidal field bending magnets. The trapped electrons then grad-B drift vertically toward the plasma interior until they are detrapped, charging the plasma negative. Calculations indicate that the highly perpendicular velocity electrons can remain stable against kinetic instabilities in the regime of interest for tokamak experiments. The penetration distance can be controlled by controlling the "ripple mirror ratio", the energy of the injected electrons, and their v.sub..perp. /v.sub.51 ratio. In this scheme, the poloidal torque due to the injected radial current is taken by the magnets and not by the plasma. Injection is accomplished by the flat cathode containing an ECH cavity to pump electrons to high v.sub..perp..

Abstract: A method and apparatus for generating and utilizing a compound plasma configuration is disclosed. The plasma configuration includes a central toroidal plasma with electrical currents surrounded by a generally ellipsoidal mantle of ionized particles or electrically conducting matter. The preferred methods of forming this compound plasma configuration include the steps of forming a helical ionized path in a gaseous medium and simultaneously discharging a high potential through the ionized path to produce a helical or heliform current which collapses on itself to produce a toroidal current, or generating a toroidal plasmoid, supplying magnetic energy to the plasmoid, and applying fluid pressure external to the plasmoid. The apparatus of the present invention includes a pressure chamber wherein the compound plasma configuration can be isolated or compressed by fluid or other forms of mechanical or magnetic pressure.

Abstract: A fusion power generating device is disclosed having a relatively small and inexpensive core region which may be contained within an energy absorbing blanket region. The fusion power core region contains apparatus of the toroidal type for confining a high density plasma. The fusion power core is removable from the blanket region and may be disposed and/or recycled for subsequent use within the same blanket region. The high density plasma produces a large radiation and particle flux on the first wall of the plasma core region thereby necessitating replacement of the core from the blanket region from time to time. A series of disposable and replaceable central core regions are disclosed for a large-scale economical electrical power generating plant.

Abstract: A reversed field pinch apparatus is equipped with a first OH coil and a second OH coil which are inductively coupled with a plasma. The first OH coil is supplied a low-level alternating current for performing F-.THETA. pumping, while the second OH coil is supplied a high-level direct current for forming a plasma current.

Abstract: A radial electric field of a desired magnitude and configuration is created hroughout a substantial portion of the cross-section of the plasma of a tokamak. The radial electric field is created by injection of a unidirectional electron beam. The magnitude and configuration of the radial electric field may be controlled by the strength of the toroidal magnetic field of the tokamak.