Abstract: Process for decontaminating exhaust gas from a fusion reactor fuel cycle of exhaust gas components containing at least one heavy hydrogen isotope selected from tritium and deuterium in compound form, in which the at least one heavy hydrogen isotope is liberated from its compound, separated out from the exhaust gas and fed back into the fuel cycle, the compound form being at least one compound which is ammonia or a hydrocarbon, comprising:(a) converting the at least one heavy hydrogen-containing compound into its elements in the exhaust gas by cracking the at least one heavy hydrogen containing compound with a cracking medium to liberate the hydrogen isotope,(b) passing the liberated hydrogen isotope through a membrane to separate out the liberated hydrogen isotope from the flow of the remaining exhaust gas, and(c) discharging the remaining decontaminated exhaust gas into the surrounding air.

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: Apparatus is provided for generating energy in the form of laser radiation. A tokamak fusion reactor is provided for generating a long, or continuous, pulse of high-energy neutrons. The tokamak design provides a temperature and a magnetic field which is effective to generate a neutron flux of at least 10.sup.15 neutrons/cm.sup.2.s. A conversion medium receives neutrons from the tokamak and converts the high-energy neutrons to an energy source with an intensity and an energy effective to excite a preselected lasing medium. The energy source typically comprises fission fragments, alpha particles, and radiation from a fission event. A lasing medium is provided which is responsive to the energy source to generate a population inversion which is effective to support laser oscillations for generating output radiation.

Abstract: Process for decontaminating an exhaust gas from a fusion reactor fuel cycle of exhaust gas components containing at least one heavy hydrogen isotope selected from tritium and deuterium in compound form, the compound form being ammonia and hydrocarbon, the exhaust gas containing CO and hydrogen isotopes and in which the at least one heavy hydrogen isotope is liberated from its compound, separated out from the exhaust gas and fed back into the fuel cycle, comprising(a) carrying out a catalytic oxidation reaction at a temperature of from 200.degree. C. to 250.degree. C., to oxidize the exhaust gas components, without changing the ammonia, as follows: CO to CO.sub.2, hydrocarbon to CO.sub.2 +water, and the hydrogen isotopes to water,(b) bringing the gas admixture resulting from step (a) into contact with a metal bed at a temperature in the range of 200.degree. C. to 400.degree. C. to selectively transform the water into hydrogen isotopes and to remove O.sub.

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: A high-power-density laser or charged-particle-beam fusion reactor system maximizes the directed kinetic energy imparted to a large mass of liquid lithium by a centrally located fusion target. A fusion target is embedded in a large mass of lithium, of sufficient radius to act as a tritium breeding blanket, and provided with ports for the access of beam energy to implode the target. The directed kinetic energy is converted directly to electricity with high efficiency by work done against a pulsed magnetic field applied exterior to the lithium. Because the system maximizes the blanket thickness per unit volume of lithium, neutron-induced radioactivities in the reaction chamber wall are several orders of magnitude less than is typical of other fusion reactor systems.

Abstract: A plasma device for use in controlling nuclear reactions within the plasma including a first wall and blanket formed in a one-piece structure composed of a solid solution containing copper and lithium and melting above about 500.degree. C.

Abstract: A fusion blanket includes a chamber wall, a multiplication section, an enrichment section and a reflector in radially outward succession, respectively. The chamber wall isolates the fusion reaction chamber from the remainder of the blanket. Fusion neutrons bombard atoms in the multiplication section to free further neutrons which are then available for breeding fuel. The enrichment section contains fertile fuel of sufficient dilution to maximize the enrichment rate and minimize fast fission. Materials may be included in the multiplication section and the enrichment section to reduce thermal neutron flux, thereby suppressing thermal fission. Additionally, tritium may be bred in both sections. The fertile material is exposed to neutron bombardment until the desired enrichment is achieved. The particles may be removed and mixed to minimize nonuniformities in enrichment. The particles may then be fabricated into fuel elements for fission reactors.

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: Two ion beams are accelerated on coincident paths in high vacuum with particle velocity vectors at 180.degree. relative to one another to increase collison and fusion probabilities. The ion beams may be of the same or of different polarities and may both be the same isotope, or may be respectively of deuterium and tritium. A heat exchange fluid such as liquid lithium is in heat exchange contact with the vacuum chamber to remove energy generated by fusion reactions between colliding and fusing particles of the two beams. The velocity vectors of the beams are controlled over a narrow range in both magnitude and direction so that there is sufficient energy to encourage the fusion reaction but not so high as to cause the particles to have elastic collisions. The intersecting or coincident beams may move linearly toward one another or may move in identical circular paths having the identical geometry or paths which intersect at at least one point.

Abstract: An arrangement is provided for controlling neutron albedo in toroidal fusion devices having inboard and outboard vacuum vessel walls for containment of the neutrons of a fusion plasma. Neutron albedo material is disposed immediately adjacent the inboard wall, and is movable, preferably in vertical directions, so as to be brought into and out of neutron modifying communication with the fusion neutrons. Neutron albedo material preferably comprises a liquid form, but may also take pebble, stringer and curtain-like forms. A neutron flux valve, rotatable about a vertical axis is also disclosed.

Abstract: A heat shield for high thermal loading and particularly pulse heat loading n fusion reactors e.g. as first wall, plasma physics installations, particle accelerators, etc. contains a cooled support plate carrying a large number of shielding or limiter members on its side facing a heat source, e.g. a hot plasma. The shielding or limiter members are detachably connected to the support plate by a good thermally conducting seat, e.g. a bevel, ball or flat seat. By suitably shaping and arranging the limiter members, it is possible to substantially cover the surfaces of practically any desired shape such as, e.g., the inner wall of a toroidal vacuum vessel. As a result of their limited size, the limiter members can be adapted in a optimum manner to locally differing requirements. The size and shape of the support member can be adapted to widely differing boundary conditions.

Abstract: A fusion reactor (10) includes a sphere (12). Structure (20) is disposed within the interior of the sphere (12) for producing a magnetic field. Structure (24, 26) is circumferentially disposed around the exterior of the sphere (12) for producing a countermagnetic field. Structure (28, 32, 38, 46a) is provided for injecting a gas containing fusible ions into the sphere (12). Structure (30, 32, 38, 46) is also provided for heating the gas within the interior of the sphere (12). Structure (62, 64, 66, 68) is provided for extracting heat from the sphere (12).

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: 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 heat absorber structure comprises a first wall of a good heat conducting material which has a surface with a plurality of spaced apart web portions with coolant channels defined between the web portions and a second wall of a good conducting material overlying the first wall and secured to at least portions of the web portions of the first wall. A second wall has a plurality of bulge portions formed therein in locations overlying the coolant channels. With the method of the invention the coolant channels are filled with an electrically conductive wax which is heated while the second wall is constrained in certain areas so as to form bulge portions on the second wall overlying the channels.

Abstract: A composition is described useful in the production of tritium in a nuclear eactor. Lithium aluminate particles are dispersed in a matrix of zirconium. Tritium produced by the reactor of neutrons with the lithium are absorbed by the zirconium, thereby decreasing gas pressure within capsules carrying the material.

Abstract: Process and apparatus for liberation of energy by controlled nuclear fusion reaction involving isotopes of hydrogen gas. Highly ionized hydrogen gas containing a higher proportion of deuterium than in naturally occurring hydrogen is pressurized, together with an oxidizing gas within combustion chamber of reciprocating piston and cylinder engine. An electrical discharge within the combustion chamber causes generation of heat by atomic dissociation and exothermal recombination of hydrogen atoms and electrical excitation of ionized gas. Ionized deuterium in the hydrogen gas undergoes a nuclear fusion reaction with consequent liberation of heat energy and remaining hydrogen gas burns in the oxidizing gas to provide control on fusion reaction. Apparatus for producing ionized hydrogen gas in appropriate form by treatment of normal industrial hydrogen gas is disclosed, and also gas mixing apparatus for mixing the ionized hydrogen with atmospheric air as the oxidizing gas.

Abstract: A process to produce energy with the fusion of hydrogen and carbon in a thermonuclear fusion reaction with an extension, wherein carbon targets are bombarded with a beam of fast protons at temperatures of 457 kev. The thermonuclear fusion reaction produces two helium atoms and two neutron particles.The neutrons are captured by a blanket of lithium 7 which cools the walls and carries the heat to a turbulent heat exchanger, then to a generator and turbine complex which generates energy, giving tritium as a sub-product.The helium atoms plus alpha particles and protons are extracted to the reactor's extension where, combined with the tritium emitted in the first cycle of the thermonuclear fusion reactor, they go to generate more energy.This process becomes self-maintaining once the thermonuclear fusion reactor is put into operation.

Abstract: A heat transfer panel provides redundant cooling for fusion reactors or the like environment requiring low-mass construction. Redundant cooling is provided by two independent cooling circuits, each circuit consisting of a series of channels joined to inlet and outlet headers. The panel comprises a welded joinder of two full-size and two much smaller partial-size sheets. The first full-size sheet is embossed to form first portions of channels for the first and second circuits, as well as a header for the first circuit. The second full-sized sheet is then laid over and welded to the first full-size sheet. The first and second partial-size sheets are then overlaid on separate portions of the second full-sized sheet, and are welded thereto. The first and second partial-sized sheets are embossed to form inlet and outlet headers, which communicate with channels of the second circuit through apertures formed in the second full-sized sheet.

Abstract: A packed fluidized bed blanket for a fusion reactor providing for efficient radiation absorption for energy recovery, efficient neutron absorption for nuclear transformations, ease of blanket removal, processing and replacement, and on-line fueling/refueling.The blanket of the reactor contains a bed of stationary particles during reactor operation, cooled by a radial flow of coolant. During fueling/refueling, an axial flow is introduced into the bed in stages at various axial locations to fluidize the bed. When desired, the fluidization flow can be used to remove particles from the blanket.

Abstract: An inert gas fuel consisting essentially of a precise, homogeneous mixture of helium, neon, argon, krypton and xenon. Apparatus for preparing the fuel includes a mixing chamber, tubing to allow movement of each inert gas into and through the various stages of the apparatus, a plurality of electric coils for producing magnetic fields, an ion gauge, ionizers, cathode ray tubes, filters, a polarizer and a high frequency generator. An engine for extracting useful work from the fuel has at least two closed cylinders for fuel, each cylinder being defined by a head and a piston. A plurality of electrodes extend into each chamber, some containing low level radioactive material. The head has a generally concave depression facing a generally semi-toroidal depression in the surface of the piston. The piston is axially movable with respect to the head from a first position to a second position and back, which linear motion is converted to rotary motion by a crankshaft.

Abstract: Atomic nuclei undergo fusion reactions by forming two beams of fusible ions traveling at fusion producing velocities opposed in rotation along spiral paths having common axes (35a), common radii and occupy common space in a reaction zone (22) for fusion producing collisions of ions in one beam with ions in the other beam.Means including sources (16 and 17) produce the oppositely traveling circumferential beams.Radially directed electric fields are applied to the beams of strength increasing with increasing distance from sources (16 and 17) for beam compression into spiral paths of a common reduced diameter passing through common space in zone (22) to promote collisions between ions in the oppositely traveling beams as they travel in the common space.

Abstract: A heat pipe configuration for use in a magnetic field environment of a fusion reactor. Heat pipes for operation in a magnetic field when liquid metal working fluids are used are optimized by flattening of the heat pipes having an unobstructed annulus which significantly reduces the adverse side region effect of the prior known cylindrically configured heat pipes. The flattened heat pipes operating in a magnetic field can remove 2--3 times the heat as a cylindrical heat pipe of the same cross sectional area.

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 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: 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 clearing thermal barrier regions of trapped ions in a tandem mirror fusion reactor apparatus utilizing a bend at each end of the cylindrical plasma chamber within which bend the thermal barrier is positioned. Ions trapped in said thermal barrier are caused by said bend to drift in a direction perpendicular to the incident magnetic field and the direction of centrifugal force, such that said ions are enabled to be collected in a divertor positioned along said ion drift path.

Abstract: The invention pertains to the method and apparatus for the confining of a stream of fusible positive ions at values of density and high average kinetic energy, primarily of tightly looping motions, to produce nuclear fusion at a useful rate; more or less intimately mixed with the fusible ions will be lower-energy electrons at about equal density, introduced solely for the purpose of neutralizing the positive space charge of the ions. Ions under high kinetic energy are introduced into an annular reaction chamber having a primarily axial strong magnetic field and an essentially radial electric field and assume in the chamber a quasi-trochoidal motion in which the kinetic energies in their small diameter looping components of motion are greater by at least an order of magnitude, than the kinetic energies in the relatively slow crossed field advance motions with which the ions circulate circumferentially around the axis of the annular reaction chamber.

Abstract: Apparatus for protecting the inner wall of a fusion chamber from microexplosion debris, x-rays, neutrons, etc. produced by deuterium-tritium (DT) targets imploded within the fusion chamber. The apparatus utilizes a fluidized wall similar to a waterfall comprising liquid lithium or solid pellets of lithium-ceramic, the waterfall forming a blanket to prevent damage of the structural materials of the chamber.

Abstract: A falling bed of ceramic particles receives neutron irradiation from a neutron-producing plasma and thereby transports energy as heat from the plasma to a heat exchange location where the ceramic particles are cooled by a gas flow. The cooled ceramic particles are elevated to a location from which they may again pass by gravity through the region where they are exposed to neutron radiation. Ceramic particles of alumina, magnesia, silica and combinations of these materials are contemplated as high-temperature materials that will accept energy from neutron irradiation. Separate containers of material incorporating lithium are exposed to the neutron flux for the breeding of tritium that may subsequently be used in neutron-producing reactions. The falling bed of ceramic particles includes velocity partitioning between compartments near to the neutron-producing plasma and compartments away from the plasma to moderate the maximum temperature in the bed.

Abstract: A thermonuclear fusion reactor assembly consisting of a plurality of TRISOPS theta pinch units arranged in a parallel configuration inside a common magnetic guide field and provided with a common surrounding FLIBE or other suitable molten metal blanket. The primary magnetic guide field is generated by a superconducting magnet assembly surrounding the container in which the bundle of fusion sticks is mounted. A gas distributing valve mechanism is employed to independently and selectively supply gas and purge same in the respective fusion stick units, and an electrical switching mechanism is employed to similarly independently and selectively energize the fusion stick units in a desired timing pattern.

Abstract: A hydrogen permeation resistant barrier is formed by diffusing aluminum into an iron or nickel alloy and forming an intermetallic aluminide layer.

Abstract: For use in a tokamak fusion reactor having a midplane magnetic coil on the inner wall of an evacuated toriodal chamber within which a neutral beam heated, fusing plasma is magnetically confined, a neutral beam armor shield and plasma limiter is provided on the inner wall of the toroidal chamber to shield the midplane coil from neutral beam shine-thru and plasma deposition. The armor shield/plasma limiter forms a semicircular enclosure around the midplane coil with the outer surface of the armor shield/plasma limiter shaped to match, as closely as practical, the inner limiting magnetic flux surface of the toroidally confined, indented, bean-shaped plasma. The armor shield/plasma limiter includes a plurality of semicircular graphite plates each having a pair of coupled upper and lower sections with each plate positioned in intimate contact with an adjacent plate on each side thereof so as to form a closed, planar structure around the entire outer periphery of the circular midplane coil.

Abstract: A breeder material for use in a breeder blanket of a nuclear reactor is disclosed. The breeder material comprises a core material of lithium containing ceramic particles which has been coated with a neutron multiplier such as Be or BeO, which coating has a higher thermal conductivity than the core material.

Abstract: A method of controlling the reaction rates of the fuel atoms in a fusion reactor comprises the step of polarizing the nuclei of the fuel atoms in a particular direction relative to the plasma confining magnetic field. Fusion reaction rates can be increased or decreased, and the direction of emission of the reaction products can be controlled, depending on the choice of polarization direction.

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 first wall construction for a tokamak reactor is disclosed, comprising a series of hollow lobes, each having a pair of side wall portions with a curved end wall portion extending therebetween. Each lobe is adapted to withstand substantial pressure on the concave side of the curved end wall portion while withstanding substantial heat flux on the convex side. The curved end wall portion has a shape which is approximately cylindrical in curvature but differs from being circular in curvature by a substantial deviation, in that such curved end wall portion is flatter in curvature than a truly circular curvature by the amount of such deviation, such that the thermal stresses generated in the curved end wall portion by such heat flux are at least approximately balance or neutralized by the bending stresses generated in such curved end wall portion by such pressure. The curvature may correspond generally in shape to the flatter half of an ellipse.

Abstract: An apparatus and method for simulating a fusion environment on a first wall or blanket structure. A material test specimen is contained in a capsule made of a material having a low hydrogen solubility and permeability. The capsule is partially filled with a lithium solution, such that the test specimen is encapsulated by the lithium. The capsule is irradiated by a fast fission neutron source.