Abstract: A fusion reactor includes an enclosure having a first end, a second end, and a midpoint substantially equidistant between the first and second ends of the enclosure. The fusion reactor includes two internal magnetic coils suspended within the enclosure and positioned on opposite sides of the midpoint of the enclosure, one or more encapsulating magnetic coils positioned on each side of the midpoint of the enclosure, two mirror magnetic coils positioned on opposite sides of the midpoint of the enclosure, and one or more cooling lines within each of the internal magnetic coils. The cooling lines carry a coolant and are operable to remove heat from the internal magnetic coils. The one or more encapsulating magnetic coils and the two mirror magnetic coils are coaxial with the internal magnetic coils. The magnetic coils are operable, when supplied with electric currents, to form magnetic fields for confining plasma within the enclosure.

Abstract: In one embodiment, a fusion reactor includes two internal magnetic coils suspended within an enclosure, a center magnetic coil coaxial with the two internal magnetic coils and located proximate to a midpoint of the enclosure, a plurality of encapsulating magnetic coils coaxial with the internal magnetic coils, and two mirror magnetic coil coaxial with the internal magnetic coils. The fusion reactor is configured to vary electrical currents supplied to the magnetic coils to heat the plasma confined within the magnetic wall.

Abstract: In one embodiment, a fusion reactor includes a plurality of internal magnetic coils suspended within an enclosure, one or more center magnetic coils coaxial with the plurality of internal magnetic coils, a plurality of encapsulating magnetic coils coaxial with the internal magnetic coils, and a plurality of mirror magnetic coils coaxial with the internal magnetic coils. The encapsulating magnetic coils maintain a magnetic wall that prevents plasma within the enclosure from expanding.

Abstract: Respective pulsed power supplies for plasma opening switches each produce a first current and a second current during a power pulse and a difference between the first current and the second current during a terminal portion of the power pulse. The pulsed power supplies are initiated or adjusted in response to measured opening times of the plasma opening switches in order to minimize or eliminate a need for command triggered opening of the plasma opening switches. Command triggered opening may occur in real time for a shot as needed in response to asymmetry of opening times of the plasma opening switches in the array during the shot.

Abstract: A pulsed power system has an inductive energy storage circuit (42) including a current source (43) and a plasma opening switch (44). The plasma opening switch has a transmission line (51, 52) coupling the current source to a load (41). The plasma opening switch changes from a closed state to an open state when a plasma discharge (45) in the plasma opening switch is driven by magnetic force from a first region along the transmission line to a second region towards the load. Electrical conductors (47, 48) are arranged for providing a stabilizing magnetic field configuration in the first region to magnetically latch the plasma discharge in the first region during charging of the inductive energy storage circuit, and current flowing along the transmission line from the current source to the load tends to disrupt the stabilizing magnetic field configuration and unlatch the plasma discharge from the first region and drive the plasma discharge toward the second region.

Abstract: A shim coil design technique determines a position and a geometry of a room temperature (RT) shim coil to provide both a desired field homogeneity and a desired B0 field setting time. The simultaneous satisfaction of both field homogeneity and field settling time is achieved without a reduction of flux leakage from the shim coil, modification of main magnet protection circuitry, and without necessarily decoupling of the shim coil from the overall main magnet.

Abstract: A system and apparatus for a magnetized plasma nuclear fusion reactor, incorporating special design features which induce a plasma heat engine cycle in a rapidly rotating plasma. The heat engine operates either continuously or by oscillations. A continuous heat engine is formed in the open field outside a field reversed configuration. The oscillatory system operates in synchronism with cyclic acceleration, collision, and deceleration of plasma masses to produce nuclear fusion reactions at an economically useful rate with a relatively small driving power required. A special magnetic field design is combined with applied electrical voltages at the end of the field lines to produce required conditions. Design features allow recovery of large fraction of collision heat which would otherwise be dissipated as a parasitic loss.

Abstract: A high energy toroidal inductor addresses not only the desire for reduced weight and volume, but also the desire for minimal stray magnetic fields. Specifically, the high energy toroidal inductor includes a bucking cylinder and a predetermined number of leaves. Each leaf is of a two-ended, twisted ring configuration and includes a top portion. The top portion is the narrowest portion of the leaf, and the width of the leaf graduates outward from the top portion to each end of the ring. The bucking cylinder interfaces with each of the leaves and presents the leaves in a side-by-side, continuous toroidal configuration.

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: Magnetic System consist from twenty Magnetic Cells and their centers connection represent right dodecahedron. Magnetic System located inside reactor filled with hydrogen with needed beginning pressure and temperature. Magnetic Cell has inside minimum three arcs (10) from radioactive substance. These arcs emitted alpha particles. Arcs (10) located evenly on the same distances around Magnetic Cell's center and inside cases (11). Arcs only one side open. This side open to the Magnetic Cell's center, Holder (12) fasten with cases(11). Also holder intend to locate Magnetic Cell in the needed position.

Abstract: A method and apparatus for the steady-state measurement of poloidal magnetic field near a tokamak plasma, where the tokamak is configured with respect to a cylindrical coordinate system having z, phi (toroidal), and r axes. The method is based on combining the two magnetic field principles of induction and torque. The apparatus includes a rotor assembly having a pair of inductive magnetic field pickup coils which are concentrically mounted, orthogonally oriented in the r and z directions, and coupled to remotely located electronics which include electronic integrators for determining magnetic field changes. The rotor assembly includes an axle oriented in the toroidal direction, with the axle mounted on pivot support brackets which in turn are mounted on a baseplate. First and second springs are located between the baseplate and the rotor assembly restricting rotation of the rotor assembly about its axle, the second spring providing a constant tensile preload in the first spring.

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: Magnetic point pole placements in a generally spherical arrangement of electromagnets forms a magnetic field. The magnetic arrangements use five regular geometric structures and geodesic triacon breakdowns of these geometric structures. Magnets are placed at the corners of each of the solids, oriented along the radii of the solid, with similar poles pointing inward. The magnets are at the same distance from structure center, and are identical in length and strength. Magnetic vector maps of fields within the structures are compared to current magnetic mirror plasma confinement fields. Non-symmetrical arrangements of magnets using regular geometric structures include specific magnets removed and new magnets added, resulting in a local monopole magnetic field and local inner field reversed mirror, depending on whether just one or both poles of the additional magnet are within the structure. Finally, the nesting of solids is presented.

Abstract: A superconductive apparatus having therein at least a superconductive member includes a lithium containing member so as to interrupt neutrons directed to the superconductive member.

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: An apparatus for increasing the collisions of nuclear particles in a "migma" type device. This device employs ring magnets to reflect ions of energies coming from the ring axis back to the ring axis on orbits that precess around the axis. In this manner collisions can be made to occur at rates which are high enough to yield useful quantities of energy or other desired products.

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 large toroidal vacuum chamber for plasma generation and confinement is lined with a toroidal blanket for shielding using modules segmented in the toroidal direction. To provide passive stabilization in the same manner as a conductive vacuum chamber wall, saddle-shaped conductor loops are provided on blanket modules centered on a midplane of the toroidal chamber with horizontal conductive bars above and below the midplane, and vertical conductive legs on opposite sides of each module to provide return current paths between the upper and lower horizontal conductive bars. The close proximity of the vertical legs provided on adjacent modules without making physical contact cancel the electromagnetic field of adjacent vertical legs. The conductive bars spaced equally above and below the midplane simulate toroidal conductive loops or hoops that are continuous, for vertical stabilization of the plasma even though they are actually segmented.

Abstract: A plasma confinement system comprising a toroidal vacuum chamber, a toroidal coil which generates a magnetic field in a toroidal direction within the vacuum chamber, current transformer coils which are wound in the toroidal direction, equilibrium magnetic field coils which are wound in the toroidal direction in order to control a plasma, alternating current coils which are wound mainly in the toroidal direction and through which alternating currents are caused to flow for enabling forming and rotating of a deformed magnetic surface and for causing rotation of the plasma in a poloidal direction, and power sources which cause currents to flow through the various coils.

Abstract: A magnetic coil arrangement for fusion reactors, wherein toroidal field coils and poloidal field coils are combined, the current paths of the toroidal field coils being led helically around the central axis of the fusion reactor at an angle of contact adapted to the requirements in each case. The current paths of the toroidal coils in this way generate at the same time a poloidal field. This achieves an energy saving with the same reactor parameters. Furthermore, the coil system can be supplemented with additional integrated or independent toroidal and poloidal field coils.

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 nuclear fusion apparatus comprises a central support stay device having a central support stay portion and a plurality of radial portions radially extending from the central support stay portion and circumferentially spaced from each other at predetermined angles, a plurality of poloidal coils disposed in the circumferential direction of the central support stay device and supported by the radial portions, and a plurality of toroidal coils radially disposed around the central support stay device and adjacent the radial outer ends of the radial portions.

Abstract: A modular tokamak system comprised of a plurality of interlocking moldules. Each module is comprised of a vacuum vessel section, a toroidal field coil, moldular saddle coils which generate a poloidal magnetic field and ohmic heating coils.

Abstract: A coil arrangement for a nuclear fusion apparatus comprises a return conductor radially penetrating through a coil at a portion having a transition between turns and a feed conductor symmetrically arranged with regard to the axis of the return conductor. The coil arrangement practically reduces current loops generated by the transition current, thereby practically reducing the generation of the error magnetic fields and, therefore, better confining the plasma.

Abstract: The coil arrangement of a nuclear fusion apparatus according to the present invention comprises a return conductor divided into two lines, one of which is connected to resistance-inductance adjuster. The resistance-inductance adjuster is adapted to adjust the current distribution, thereby considerably reducing the error magnetic field generated to improve the characteristic of plasma confinement.

Abstract: Metallic insulation for superconducting magnets to provide coil to coil and pancake insulation. Exemplary metal alloys and an anodization coating for such insulation are identified and may be selectively removed to provide shunt current paths. The coating for such insulation may be selectively removed to provide shunt current paths when the coil experiences a quench condition to preclude coil damage. Various applications of metallic insulation to superconducting coils are discussed.

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: 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: 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: A poloidal coil arrangement for a nuclear fushion apparatus comprises at least two poloidal coil sections each including a plurality of conductor turns, and a plurality of bridging joining members for electrically and metallurgically joining the turn ends of the conductor turns to form a plurality of complete turns. The joining members have end surfaces shaped such that the joining members can be supported by the end surfaces of the conductor turns. The length in the circumferential direction of the top side of each joining member is nearly equal to or shorter than the length in the circumferential direction of the opposing lower side of the upper joining member located above that joining member.

Abstract: A magnetically-conductive filler material bridges the gap between a multi-part magnetic shield structure which substantially encloses a predetermined volume so as to minimize the ingress or egress of magnetic fields with respect to that volume. The filler material includes a heavy concentration of single-magnetic-domain-sized particles of a magnetically conductive material (e.g. soft iron, carbon steel or the like) dispersed throughout a carrier material which is generally a non-magnetic material that is at least sometimes in a plastic or liquid state. The maximum cross-sectional particle dimension is substantially less than the nominal dimension of the gap to be filled. An epoxy base material (i.e. without any hardening additive) low volatility vacuum greases or the like may be used for the carrier material.

Abstract: A nuclear fusion reactor has a toroidal, electrically conductive shell and an air-core current transformer coil with a single turn disposed on the outer peripheral side of the shell, a plurality of port holes provided in the shell to be radially aligned with those in the coil respectively, the shell and the coil being coated with electrically insulating layers of the FBC type except for each of the port holes and its adjacent portion which are electrically insulated by one pair of electrically insulating insertions having cylindrical sections fitted into the port hole from both ends to be superposed on each other and flange sections radially extending from the opposite ends of the superposed cylindrical sections and disposed on the opposite surface portions of the shell or the coil adjacent to the port hole, and connected to the mating electrically insulating layer portions, the flange sections located on the shell and the coil to oppose to each other having terminations spaced from each other by a predetermi

Abstract: A toroidal coil apparatus which includes a plurality of coil support frames which contain coils and which are radially arranged with wedge surfaces of wedge-like coupling portions juxtaposed to each other at the inner end portions thereof, flanges formed along straight portions of said support frames inside the torus, bands that engage across a predetermined number of said flanges to fasten said support frames which are neighboring to one another, thereby to constitute blocks; and coupling members which are arranged inside the torus and which firmly couple the blocks together.

Abstract: The present invention relates to a toroidal coil apparatus including a plurality of coil support frames which contain coils having wedge-like coupling portions at the inner end portions thereof, reinforcing members which are provided at portions off the straight portions of the coil support frames and in the vicinity thereof, the reinforcing members having keyways and spaces to couple and fasten said coil support frames together, keys that are inserted in the keyways of the reinforcing members to couple the coil support frames together, and bolts that are screwed into the reinforcing members at the portions thereof backed by spaces to rigidly secure the coil support frames.

Abstract: A helical axis stellarator using only noninterlocking planar, non-circular coils, generates magnetic fields having a magnetic well and large rotational transform with resultant large equilibrium beta.

Abstract: A coolant arrangement is disclosed for magnetic coil turn assemblies in which cooling fluid is flowed through a supply header along the face of a coil turn and into coolant inlet openings positioned along the face of the coil turn beneath the supply header structure. Coolant is directed through coolant channels around the magnetic coil turn, and into outlet openings. The outlet openings are in fluid communication with a return header also positioned on a flat face of a magnetic coil turn. There is also disclosed a method and apparatus for passing coolant through adjacent coolant channels in a magnetic coil turn in opposite directions. The cooling means disclosed avoids creating hot spots in the vicinity of the coolant inlets and outlets and reduces stresses in the coil in the vicinity of the coolant inlets and outlets. It also provides for maintaining a uniform average temperature throughout the coil turn.

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: 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: A compression hub (10) for use in a fusion reactor system comprising a multiplicity of compression plates (24, 24') that are polygonal in configuration, and which are arranged in vertically stacked, substantially abutting relation to each other. The compression plates (24, 24') are suitably interconnected, such as by welding, around the periphery thereof so as to provide a compression hub (10) that is in the form of a unitary structure. Each of the compression plates (24, 24') is provided with fluid flow means (30, 32, 30', 32'). The fluid flow means (30, 32, 30', 32') of the compression plates (24, 24') cooperate with one another to establish a fluid flow path for coolant through the compression hub (10). Each of the compression plates (24, 24') is further provided with eddy current prevent means operable to impede the circulation through the plates (24, 24') of eddy currents induced by changes in the magnetic flux field.

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 electrical discharge thermonuclear reactor having a capacitor which is discharged into a reaction chamber through a low inductance distribution circuit funneling discharge current to a focus point in the reaction chamber so that the magnitude of the magnetic field intensity associated with the discharge current is generally inversely proportional to the square of the distance from the focus point. Then the circuit inductance is limited to a minimum value regardless of the absolute maximum distance from the capacitor to the focus point and thus the size of the capacitor. The distribution circuit has two outward-branching, interpenetrating three dimensional circuit networks of opposite polarity conveniently fabricated by stacking conductor plates having a generally cylindrical geometry.

Abstract: The inside, outside and opposite side surfaces of elongate, helical shaped, rectangular cross-section metal work pieces are individually close tolerance machined to produce finished conductor segments. These segments are connected end to end to form a helical coil which encircles a toroidal conducting shell of a fusion reactor. An apparatus is provided which may be fitted with corresponding tooling for separately machining the inside and outside surfaces of a work piece. The work piece is supported by the apparatus with the surface to be machined unobstructed. The unobstructed surface is cut in the poloidal direction as the work piece is moved in the toroidal direction. The side surfaces of the work piece are machined with a programmable, numerically controlled milling machine.

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 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-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: Disclosed is a superconductive electromagnet apparatus having a coil with a coiled conductor with a channel between adjacently disposed the paths of the coil conductor of which width is selected in accordance with amounts of heat produced at the corresponding portions of the coil section as viewed in cross section.

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.