Abstract: A fusion device provides for the reaction of atomic nuclei, preferably deuterons and tritons, to generate reaction products with kinetic energies convertible to useful energy. First and second sources of first and second positive ions provide such ions at temperatures in a range where the ions have a substantially optimum cross section for mutual reaction. The respective ions are accelerated to substantially the same mean velocity and formed into respective beams. The beams are neutralized and directed into a portion of a reaction chamber substantially orthogonally of a substantially constant unidirectional magnetic field as first and second polarized beams of respective first and second positive hot ions. The polarization of the first and second polarized beams is drained, preferably by a plasma created in the portion of the reaction chamber, to separate the neutralizing electrons from the respective first and second positive hot ions.

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 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. Thermonuclear ignition of the plasma is obtained by feeding neutral fusible gas into the plasma in a controlled manner such that charged particle heating produced by the fusion reaction is utilized to bootstrap the device to a region of high temperatures and high densities wherein charged particle heating is sufficient to overcome radiation and thermal conductivity losses. 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.

Abstract: Apparatus is provided for generating energy in the form of light radiation. A fusion reactor is provided for generating a long, or continuous, pulse of high-energy neutrons. The neutron flux is coupled directly with the lasing medium. The lasing medium includes a first component selected from Group O of the periodic table of the elements and having a high inelastic scattering cross section. Gamma radiation from the inelastic scattering reactions interacts with the first component to excite the first component, which decays by photon emission at a first output wavelength. The first output wavelength may be shifted to a second output wavelength using a second liquid component responsive to the first output wavelength. The light outputs may be converted to a coherent laser output by incorporating conventional optics adjacent the laser medium.

Abstract: An apparatus and method for maintaining a steady-state current in a toroidal magnetically confined plasma. An electric current is generated in an edge region at or near the outermost good magnetic surface of the toroidal plasma. The edge current is generated in a direction parallel to the flow of current in the main plasma and such that its current density is greater than the average density of the main plasma current. The current flow in the edge region is maintained in a direction parallel to the main current for a period of one or two of its characteristic decay times. Current from the edge region will penetrate radially into the plasma and augment the main plasma current through the mechanism of anomalous viscosity.In another aspect of the invention, current flow driven between a cathode and an anode is used to establish a start-up plasma current.

Abstract: A demountable tokamak fusion reactor core in which a demountable central portion contains at least the inner toroidal field producing legs of the tokamak toroidal field coil and the plasma containment vessel. Also in the demountable central portion may be poloidal field coils and a means of heating the plasma or heating and shaping the plasma, e.g., an ohmic heating coil. The outer relatively permanent portion of the fusion reactor contains a blanket system within an opening formed by the current return legs of the toroidal field coil. Different embodiments of the ohmic heating coil could include a bucking cylinder toroidal magnet support. A reactor vessel and a dynamic tokamak support and tension suppressing system supports the tokamak.

Abstract: A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam.

Abstract: An 1=1 helical winding which spirals about a conventional planar, circular central conductor of a helical-axis stellarator adds a significant degree of flexibility by making it possible to control the rotational transform profile and shear of the magnetic fields confining the plasma in a helical-axis stellarator. The toroidal central conductor links a plurality of toroidal field coils which are separately disposed to follow a helical path around the central conductor in phase with the helical path of the 1=1 winding. This coil configuration produces bean-shaped magnetic flux surfaces which rotate around the central circular conductor in the same manner as the toroidal field generating coils. The additional 1=1 winding provides flexible control of the magnetic field generated by the central conductor to prevent the formation of low-order resonances in the rotational transform profile which can produce break-up of the equilibrium magnetic surfaces.

Abstract: A toroidal fusion device with an elongated axial cross section is described which is capable of ignition without auxiliary heating and with modest toroidal magnetic field. The device is based on the principle that for elongated toroids the toroidal current density in the plasma at ignition is subject to a limit which is proportional to the product of the elongation and the toroidal magnetic field. The elongation is made greater than about 4. The aspect ratio is preferably between about 3 and 10.

Abstract: A magnetically confined helical z-pinch plasma is formed as a helicoid having an approximately D-shaped cross section, thereby generating a large transform of magnetic field line pitch suitably distributed throughout the plasma volume to aid in the reversal of field lines in the axial direction and increase magnetic shear.

Abstract: The present invention is a nuclear fusion reactor serving to contain a totally organized tritium-deuterium plasma by guiding the self-bombarding particles in a resonating path of a particular wavelength and frequency, similar to a radio wave. Under these conditions the electrons tend to remain cooler, which reduces plasma radiation energy losses. Energy may be added to the plasma by axially distributed oscillators of the proper frequency, raising the plasma to ignition temperature and densities. Finally the ignited plasma directs its high energy neutrons into strategically located lithium blankets and the ionic energy levels are controlled by causing the plasma to generate an alternating electric current. Various types of alternate fusion reactions are briefly considered.

Abstract: Cyclotron breakdown is prevented in a partially evacuated waveguide by providing a section of waveguide having an axial cut therein in order to apply a potential across the two halves of the waveguide. This section is positioned in the waveguide crossing the area of electron cyclotron resonance. The potential applied across the waveguide halves is used to deflect seed electrons into the wall of the waveguide in order to prevent ionization of gas molecules and creation of more electron ion pairs which would result in cyclotron breakdown. Support means is also disclosed for electrically isolating the waveguide halves and transition means is provided between the section of the waveguide with the axial cut and the solid waveguide at either end thereof.

Abstract: Apparatus for maintaining three-dimensional MHD equilibrium in a plasma contained in a helical axis stellerator includes a resonant coil system, having a configuration such that current therethrough generates a magnetic field cancelling the resonant magnetic field produced by currents driven by the plasma pressure on any given flux surface resonating with the rotational transform of another flux surface in the plasma. Current through the resonant coil system is adjusted as a function of plasma beta.

Abstract: For toroidal magnetic confinement devices the second region of stability against ballooning modes can be accessed with controlled operation. Under certain modes of operation, the first and second stability regions may be joined together. Accessing the second region of stability is accomplished by forming a bean-shaped plasma and increasing the indentation until a critical value of indentation is reached. A pusher coil, located at the inner-major-radius side of the device, is engaged to form a bean-shaped poloidal cross-section in the plasma.

Abstract: A rotating flux transformer which includes a magnetic core having poloidal primary and secondary windings and toroidal primary and secondary windings. Quadrature flux is produced in the magnetic core by connecting one end of the poloidal primary winding to the center of the toroidal primary winding. The quadrature flux combines vectorially to produce a rotating induction vector in the magnetic core.

Abstract: A tokamak apparatus includes an electrically conductive metal pressure vessel for defining a chamber and confining liquid therein. A liner disposed within said chamber defines a toroidal space within the liner and confines gas therein. The metal vessel provides an electrically conductive path linking the toroidal space. Liquid metal is forced outwardly through the chamber outside of the toroidal space to generate electric current in the conductive path and thereby generate a toroidal magnetic field within the toroidal space. Toroidal plasma is developed within the toroidal space about the major axis thereof.

Abstract: Apparatus and method of the invention maintain a plasma current with an oscillatory nonohmic current drive. Each cycle of operation has a generation period in which current driving energy is applied to the plasma, and a relaxation period in which current driving energy is removed. Plasma parameters, such as plasma temperature or plasma average ionic charge state, are modified during the generation period so as to oscillate plasma resistivity in synchronism with the application of current driving energy. The invention improves overall current drive efficiencies.

Abstract: A magnetic well reversed field plasma pinch method and apparatus produces hot magnetically confined pinch plasma in a toroidal chamber having a major toroidal axis and a minor toroidal axis and a small aspect ratio. A reversed magnetic field pinch current channel within the plasma and at least one hyperbolic magnetic axis outside substantially all of the plasma form thereby a region of average magnetic well in a region of nested closed magnetic surfaces surrounding the plasma current channel when the magnetic field component in the direction of the hyperbolic magnetic axis is also made to be substantially less than zero in the vicinity of the hyperbolic magnetic axis. The magnetic well reversed field pinch is operated so that reversal of the safety factor q and of the toroidal magnetic field takes place within the plasma, and the plasma so produced closely approximates known theoretical stability conditions.

Abstract: A multipole plasma pinch method and apparatus produces hot magnetically confined z-pinch plasma with a plurality of z-pinch current channels arranged so as to generate a multipolar magnetic field and at least one hyperbolic magnetic axis within the plasma space roughly enclosed by the channels, forming thereby a region of average magnetic well in a region of nested closed plasma magnetic surfaces surrounding the plasma current channels, when the magnetic field component in the direction of the hyperbolic axis is also made to be substantially zero in the vicinity of the hyperbolic axis. The multipole pinch invention may be operated so that q and field reversal take place within the plasma, and the plasma so produced closely approximates known theoretical stability conditions. The well-producing hyperbolic axis of the present invention is produced effectively by replacing the solid conducting rings of prior art multipole plasma confinement devices by z-pinch-like toroidal current channel loops of plasma.

Abstract: A composite toroidal field (TF) generating means consisting of segmented magnetic coil windings is disclosed. Each coil winding of the TF generating means consists of a copper or copper alloy conductor segment and an aluminum or aluminum alloy conductor segment. The conductor segments are joined at a high strength, low electrical resistance joint and the joint may either be a mechanical or metallurgical one. The use of the aluminum or aluminum alloy conductor segments improves the neutron economy of the reactor with which the TF coil is associated and reduces TF coil nuclear heating and heating gradients, and activation in the TF coils.

Abstract: Disclosed is a method and apparatus for controlling coolant distribution in ohmic heating and other poloidal field magnetic coils. The apparatus consists of a coolant inlet and outlet arrangement with spiral coolant channels positioned therebetween. The spiral coolant channels are designed to control the coolant pressure drop within the coil turns and hence the coolant flow distribution within the entire coil. The coolant channels of the present invention provide coil turns with improved structural and cooling characteristics over the prior art. The method disclosed consists of controlling the flow distribution of cooling fluid through coolant channels in a magnetic coil by using spiral channels of a specially designed length, width and spiral configuration.

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: Disclosed is a segmented toroidal field coil for use in a tokamak-type reactor and a method for forming the coil. Each toroidal field coil winding is segmented into two or more segments with a connection means provided at the end of each segment for electrically connecting the segments together and for joining consecutive adjacent segments. The coil segments are electrically conducting and will, therefore, induce a toroidal magnetic field when its feed points are connected to a power source. The toroidal field coil of the present invention maximizes heat flow from the plasma region of the reactor to the external blanket by eliminating bulky crossover connections from coil to coil that could otherwise restrict the heat flow. The present invention discloses a simple and efficient method for forming a toroidal field coil assembly that eliminates costly final machining such as precision twisting.

Abstract: An inductive method and apparatus for forming detached spheromak plasma using a thin-walled metal toroidal ring, with external current leads and internal poloidal and toroidal field coils located inside a vacuum chamber filled with low density hydrogen gas and an external axial field generating coil. The presence of a current in the poloidal field coils, and an externally generated axial field sets up the initial poloidal field configuration in which the field is strongest toward the major axis of the toroid. The internal toroidal-field-generating coil is then pulsed on, ionizing the gas and inducing poloidal current and toroidal magnetic field into the plasma region in the sleeve exterior to and adjacent to the ring and causing the plasma to expand away from the ring and toward the major axis. Next the current in the poloidal field coils in the ring is reversed. This induces toroidal current into the plasma and causes the poloidal magnetic field lines to reconnect.

Abstract: A fusion reactor device in which the toroidal magnetic field and at least a portion of the poloidal magnetic field are provided by a single set of modular coils. The coils are arranged on the surface of a low aspect ratio toroid in planes having the cylindrical coordinate relationship .phi.=.phi..sub.i +kz where k is a constant equal to each coil's pitch and .phi..sub.i is the toroidal angle at which the i'th coil intersects the z=o plane. The device may be described as a modular, high beta torsation whose screw symmetry is pointed along the systems major (z) axis. The toroid defined by the modular coils preferably has a racetrack minor cross section. When vertical field coils and preferably a toroidal plasma current are provided for magnetic field surface closure within the toroid, a vacuum magnetic field of racetrack shaped minor cross section with improved stability and beta valves is obtained.

Abstract: A torque structure particularly suitable for utilization in a power reactor of the Tokamak-type, and operable therein for purposes of providing support for the toroidal field (TF) coils that comprise one of the major operating components of such a Tokamak power reactor. The subject torque structure takes the form of a frame structure that is operable to enable torque loads acting on the TF coils to be equilibrated as close to the area of force application as feasible. The aforesaid torque structure includes an intercoil structure composed of spacer wedges that are interposed between each adjacent pair of TF coils. The spacer wedges, in turn, consist of bearing plates positioned between the TF coils so as to be in contacting relation therewith and a number of cross plates that are cooperatively associated with the bearing plates so as to form therewith a rigid assembly. The intercoil structure is affixed to a segmented, membrane shell that surrounds, encloses and supports the TF coil frames.

Abstract: A method and means for accelerating charged particle beams having very high current densities to relativistic energies, as, for example, embodied in a betatron capable of carrying a current of many tens of kiloamperes at energies up to at least 300 Mev. The basic principle underlying the present invention is the containment of a beam of charged particles, more particularly a beam of electrons, by a magnetic field directed along the beam. As the strength of the magnetic field is increased as a function of time the beam of electrons becomes compressed in the direction transverse to the beam into a region of high charge density. The electrons may then be accelerated along the direction of the magnetic field to form an ultra-relativistic beam. At such high energies the beam tends to be stable and the containing magnetic field is no longer necessary. The magnetic field may therefore be permitted to decay.

Abstract: A fusion-fission reactor having a plasma containing toroidal fusion region for producing high energy neutrons from fusion reactions and a region external to the fusion region containing material which is both fissile with respect to high energy neutrons and fertile with respect to low energy neutrons. The device comprises a toroidal field generating means and a region of fissile-fertile material positioned within the region of the toroidal field generating means. The toroidal field generating means is positioned substantially adjacent the toroidal fusion region.

Abstract: A fusion reactor of the toroidal-type having a plasma containing toroidal fusion region producing energy from fusion reactions and comprising a toroidal field generating means for producing a toroidal magnetic field in the fusion region upon passage of current therethrough, said toroidal field generating means positioned proximate the toroidal fusion region, and ohmic heating coils for ohmically heating the plasma wherein the ohmic heating coils are positioned between the toroidal fusion region and the toroidal field generating means.

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 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. Thermonuclear ignition of the plasma is obtained by feeding neutral fusible gas into the plasma in a controlled manner such that charged particle heating produced by the fusion reaction is utilized to bootstrap the device to a region of high temperatures and high densities wherein charged particle heating is sufficient to overcome radiation and thermal conductivity losses. 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.

Abstract: A method and apparatus for forming a detached, compact toroidally shaped spheromak plasma by an inductive mechanism. A generally spheroidal vacuum vessel (1) houses a toroidally shaped flux ring or core (2) which contains poloidal and toroidal field generating coils. A plasma discharge occurs with the pulsing of the toroidal field coil, and the plasma is caused to expand away from the core (2) and toward the center of the vacuum vessel (1). When the plasma is in an expanded state, a portion of it is pinched off in order to form a separate, detached spheromak plasma configuration. The detached plasma is supported by a magnetic field generated by externally arranged equilibrium field coils (5).

Abstract: Apparatus is provided for controlling the plasma energy production rate of a magnetic-confinement fusion reactor, by controlling the magnetic field ripple. The apparatus includes a group of shield sectors (30a, 30b, etc.) formed of ferromagnetic material which has a temperature-dependent saturation magnetization, with each shield lying between the plasma (12) and a toroidal field coil (18). A mechanism (60) for controlling the temperature of the magnetic shields, as by controlling the flow of cooling water therethrough, thereby controls the saturation magnetization of the shields and therefore the amount of ripple in the magnetic field that confines the plasma, to thereby control the amount of heat loss from the plasma. This heat loss in turn determines the plasma state and thus the rate of energy production.

Abstract: Methods and apparatus for plasma generation, confinement and control such as Tokamak plasma systems are described having a two layer field shaping coil system comprising an inner coil layer close to the plasma and an outer coil layer to minimize the current in the inner coil layer.

Abstract: Tokamak apparatus includes a pressure vessel for defining a reservoir and confining liquid therein. A toroidal liner disposed within the pressure vessel defines a toroidal space within the liner. Liquid metal fills the reservoir outside said liner. Electric current is passed through the liquid metal over a conductive path linking the toroidal space to produce a toroidal magnetic field within the toroidal space about the major axis thereof. Toroidal plasma is developed within the toroidal space about the major axis thereof.

Abstract: A tokamak apparatus includes a pressure vessel for defining a reservoir and confining liquid therein. A collapsible toroidal liner disposed within the pressure vessel defines a toroidal space within the liner. Liquid metal fills the reservoir outside said liner. A toroidal magnetic field is developed within the toroidal space about the major axis thereof. A toroidal plasma is developed within the toroidal space about the major axis thereof. Pressure is applied to the liquid metal to collapse the liner and reduce the volume of the toroidal space, thereby increasing the toroidal magnetic flux density therein.

Abstract: A toroidal plasma device has a toroidal confinement vessel defining a toroidal space and confining ionized gas therein. A solenoid which links the toroidal space induces a toroidal electric field therein to produce plasma current. A plurality of first windings are wound substantially helically around the vessel substantially equally spaced around its minor circumference. A plurality of second windings are wound substantially helically around the vessel substantially midway between successive first windings. Direct current is passed through the respective first and second windings in opposite directions with the current in the respective first and second windings equal or slightly unbalanced. The currents in the first and second windings produce a helical magnetic field.

Abstract: An Elmo bumpy square (EBS) plasma confinement device is provided by four linear sections formed of a plurality of series connected magnetic mirror confinement segments linked by four 90.degree. sections. Each 90.degree. section is formed of toroidal solenoid-type confinement windings which produce a strong curved solenoidal-type magnet field. Each magnetic mirror segment includes axisymmetric mirror field windings coupled with microwave cavities to form a linear axisymmetric bumpy magnet field, for confinement of a plasma. As in a conventional Elmo bumpy torus, each microwave cavity contains a high-beta, relativistic electron plasma ring which rotates about the confined plasma to provide magnetohydrodynamic stability of the plasma. The electron plasma ring is formed and maintained by microwave heating through the introduction of microwave energy at a specified frequency into each cavity. The 90.degree.

Abstract: Method for producing fusion power wherein a neutral beam is injected into a toroidal bulk plasma to produce fusion reactions during the time permitted by the slowing down of the particles from the injected beam in the bulk plasma.

Abstract: A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.