Abstract: A method and system for stably generating and accelerating magnetized plasma comprises ionizing an injected gas in a plasma generator and generating a formation magnetic field to form a magnetized plasma with a closed poloidal field, generating a reverse poloidal field behind the magnetized plasma and having a same field direction as a back edge of the closed poloidal field and having an opposite field direction of the formation magnetic field, and generating a pushing toroidal field that pushes the reverse poloidal field against the closed poloidal field, thereby accelerating the magnetized plasma through a plasma accelerator downstream from the plasma generator. The reverse poloidal field serves to prevent the reconnection of the formation magnetic field and closed poloidal field after the magnetized plasma is formed, which would allow the pushing toroidal field to mix with the closed poloidal field and cause instability and reduced plasma confinement.

Abstract: A tokamak comprising a toroidal containment vessel and a plasma initiation system. The toroidal containment vessel is configured to contain a plasma. The plasma initiation system comprises upper and lower poloidal field, PF, coil sets. Each PF coil set comprises at least one inner PF coil located outside of the containment vessel, an outer PF coil located inside the containment vessel, and shielding located between the outer PF coil and a location of the plasma during operation of the tokamak and configured to protect the outer PF coil from heat emitted by the plasma. The inner and outer PF coils are configured so as to form a PF null within the containment vessel between the inner and outer PF coils, such that the upper and lower PF coil pairs are operable to initiate a plasma in the containment vessel via double null merging.

Abstract: A processing chamber including multiple plasma sources in a process chamber top. Each one of the plasma sources is a ring plasma source including a primary winding and multiple ferrites. A plasma processing system is also described. A method of plasma processing is also described.

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: Disclosed is a tokamak reactor. The reactor includes a first toroidal chamber, current carrying conductors, at least one divertor plate within the first toroidal chamber and a second chamber adjacent to the first toroidal chamber surrounded by a section that insulates the reactor from neutrons. The current carrying conductors are configured to confine a core plasma within enclosed walls of the first toroidal chamber such that the core plasma has an elongation of 1.5 to 4 and produce within the first toroidal chamber at least one stagnation point at a perpendicular distance from an equatorial plane through the core plasma that is greater than the plasma minor radius. The at least one divertor plate and current carrying conductors are configured relative to one another such that the current carrying conductors expand the open magnetic field lines at the divertor plate.

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: A system and apparatus for controlled fusion in a field reversed configuration (FRC) magnetic topology and conversion of fusion product energies directly to electric power. Preferably, plasma ions are magnetically confined in the FRC while plasma electrons are electrostatically confined in a deep energy well, created by tuning an externally applied magnetic field. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions ions are fused together by the nuclear force, thus forming fusion products that emerge in the form of an annular beam. Energy is removed from the fusion product ions as they spiral past electrodes of an inverse cyclotron converter. Advantageously, the fusion fuel plasmas that can be used with the present confinement and energy conversion system include advanced (aneutronic) fuels.

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: 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 system and apparatus for controlled fusion in a field reversed configuration (FRC) magnetic topology and conversion of fusion product energies directly to electric power. Preferably, plasma ions are magnetically confined in the FRC while plasma electrons are electrostatically confined in a deep energy well, created by tuning an externally applied magnetic field. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions they are fused together by the nuclear force, thus forming fusion products that emerge in the form of an annular beam. Energy is removed from the fusion product ions as they spiral past electrodes of an inverse cyclotron converter. Advantageously, the fusion fuel plasmas that can be used with the present confinement and energy conversion system include advanced (aneutronic) fuels.

Abstract: A divertor for a TOKAMAK nuclear fusion reactor, having at least one target element for intercepting the path of contaminating particles from a toroidal channel in which plasma is formed and confined; and at least one grille structure interposed between a catch region, for catching the contaminating particles, and the input of a plasma purifying device. The grille structure is fitted with a layered structure of threadlike felt material facing the catch region and through which flows a mixture of deuterium, tritium. helium and impurities flowing through the grille structure.

Abstract: An electric field plasma pump includes a toroidal ring bias electrode (56) positioned near the divertor strike point of a poloidal divertor of a tokamak (20), or similar plasma-confining apparatus. For optimum plasma pumping, the separatrix (40) of the poloidal divertor contacts the ring electrode (56), which then also acts as a divertor plate. A plenum (54) or other duct near the electrode (56) includes an entrance aperture open to receive electrically-driven plasma. The electrode (56) is insulated laterally with insulators (63,64), one of which (64) is positioned opposite the electrode at the entrance aperture. An electric field E is established between the ring electrode (56) and a vacuum vessel wall (22), with the polarity of the bias applied to the electrode being relative to the vessel wall selected such that the resultant electric field E interacts with the magnetic field B already existing in the tokamak to create an E.times.B/B.sup.2 drift velocity that drives plasma into the entrance aperture.

Abstract: A method and apparatus for plasma relaxation under magnetic global topological constraint produces a hot magnetically confined toroidal Z-pinch plasma with a plurality of straight and toroidal relaxing plasma discharges so as to generate at least one open-ended poloidal null separatrix in the magnetic field with one poloidal null within the plasma space situated in the small major radius side of the toroidal discharge, forming thereby a magnetic configuration (called DAG) with non-zero homotopic invariant, including a toroidal reversed-field pinch with inner poloidal divertor, in a region of open plasma magnetic surfaces surrounding the toroidal discharges, when toroidal magnetic field component is also made to be substantially different from zero at the poloidal null.

Abstract: An article transporting apparatus for inserting an article into a port of a vessel and removing the article from the vessel through the port and for transporting the article in a direction transverse to the inserting and removing direction within the vessel. The apparatus includes a frame movable into and out from the vessel through the port, a parallel link mechanism mounted on the frame for transporting the article in a direction transverse to a direction of movement of the frame, a device for driving the parallel link mechanism, and a device for connecting the end of the parallel link mechanism to the article.

Abstract: A torus type nuclear fusion apparatus including a main limiter for contacting plasma generated in a space enclosed by a first wall of a blanket and maintaining the shape of plasma stable, and a sub-limiter arranged between the first wall and the outer circumference of plasma to neutralize helium ion, a product of fusion reaction.

Abstract: A device for coupling RF power (a plasma sweeper) from a phased waveguide array for introducing RF power to a plasma having a magnetic field associated therewith comprises at least one electrode positioned near the plasma and near the phased waveguide array; and a potential source coupled to the electrode for generating a static electric field at the electrode directed into the plasma and having a component substantially perpendicular to the plasma magnetic field such that a non-zero vector cross-product of the electric and magnetic fields exerts a force on the plasma causing the plasma to drift.

Abstract: A plasma confining device is provided with a deflection magnetic field device which sets magnetic flux perpendicularly to a central plane of sheet-shaped charged particle flow formed by charged particles which have escaped from a plasma confined by a cusp magnetic field or a mirror magnetic field through the line cusp or linear open end thereof, an edge of the deflection magnetic field being perpendicular to the direction of motion of the sheet-shaped charged particle flow, so that each charged particle, composing the sheet-shaped charged particle flow, is changed in its direction of motion reversely and forced to reenter into the plasma without remarkable loss.

Abstract: In a plasma containment device of a type having superconducting field coils for magnetically shaping the plasma into approximately the form of a torus, an improved divertor target for removing impurities from a "scrape off" region of the plasma comprises an array of water cooled swirl tubes onto which the scrape off flux is impinged. Impurities reflected from the divertor target are removed from the target region by a conventional vacuum getter system. The swirl tubes are oriented and spaced apart within the divertor region relative to the incident angle of the scrape off flux to cause only one side of each tube to be exposed to the flux to increase the burnout rating of the target. The divertor target plane is oriented relative to the plane of the path of the scrape off flux such that the maximum heat flux onto a swirl tube is less than the tube design flux. The containment device is used to contain the plasma of a tokamak fusion reactor and is applicable to other long pulse plasma containment systems.

Abstract: Apparatus for removing the helium ash from a fusion reactor having a D-T plasma comprises a helium trapping site within the reactor plasma confinement device, said trapping site being formed of a trapping material having negligible helium solubility and relatively high hydrogen solubility; and means for depositing said trapping material on said site at a rate sufficient to prevent saturation of helium trapping.