Abstract: A device for generating compressed fluids includes a first process chamber for a first reaction material; a second process chamber for a second reaction material; a third process chamber for a fluid intended for compression; a unit for determining the nebulization and the consequent inlet of the first reaction material into process chamber; a unit intended for determining the emission of radio waves with variable frequencies in the direction of the process chamber, where the radio waves emitted by the unit interact with the first and second reaction material contained in third process chamber, for producing a high-energy plasma warms and thereby compresses the fluid contained in second process chamber.

Abstract: A method, system, and apparatus are disclosed for a complex shape structure for liquid lithium first walls of fusion power reactor environments. In particular, the method involves installing at least one tile on the surface area of the internal walls of the reactor chamber. The tile(s) is manufactured from a high-temperature resistant, porous open-cell material. The method further involves flowing liquid lithium into the tile(s). Further, the method involves circulating the liquid lithium throughout the interior network of the tile(s) to allow for the liquid lithium to reach the external surface of the tile(s) that faces the interior of the reactor chamber. In addition, the method involves outputting the circulated liquid lithium from the tile(s). In one or more embodiments, the reactor chamber is employed in a fusion reactor. In some embodiments, the tile is manufactured from a ceramic material or a metallic foam.

Abstract: A nuclear fusion system comprises a nuclear fusion device for providing heat energy, a capacitor for storing electrical energy for use by the nuclear fusion device in providing the heat energy, and an electrical conductor for carrying electrical energy from the capacitor to the nuclear fusion device, each of the nuclear fusion device, the capacitor and the conductor being located within a first chamber. The first chamber is located within a second chamber. A fluid is located between the first and second chambers, surrounds the nuclear fusion device, the capacitor and the conductor, and receives heat energy from each of the nuclear fusion device, the capacitor and the conductor, resulting in the fluid being heated. A thermal energy converter receives heated fluid from the second chamber. A super insulating material encloses the second chamber to reduce heat loss from the heated fluid to the cooler ambient.

Abstract: A hybrid indirect-drive/direct drive for inertial confinement fusion utilizing laser beams from a first direction and laser beams from a second direction including a central fusion fuel component; a first portion of a shell surrounding said central fusion fuel component, said first portion of a shell having a first thickness; a second portion of a shell surrounding said fusion fuel component, said second portion of a shell having a second thickness that is greater than said thickness of said first portion of a shell; and a hohlraum containing at least a portion of said fusion fuel component and at least a portion of said first portion of a shell; wherein said hohlraum is in a position relative to said first laser beam and to receive said first laser beam and produce X-rays that are directed to said first portion of a shell and said fusion fuel component; and wherein said fusion fuel component and said second portion of a shell are in a position relative to said second laser beam such that said second portion

Abstract: The invention is for a system and method to reduce neutron production from a deuterium-helium-3 (D-3He) fueled, steady-state, small nuclear fusion reactor. The reactor employs a field-reversed configuration (FRC) magnetic confinement scheme and an odd-parity rotating magnetic field (RMFo) that produces periodic, co-streaming, energetic ion beams which heat the plasma. This is accomplished through radio-frequency (RF) heating, which can effectively heat and maintain the plasma. Use of this method will lessen damage to and activation of reactor components and, in doing so, can advance the development of fusion reactors for electrical, power and propulsion applications by alleviating the need for both nuclear-materials and tritium-breeding-technology testing programs.

Abstract: A method of stripping tritium from flowing stream of molten salt includes providing a tritium-separating membrane structure having a porous support, a nanoporous structural metal-ion diffusion barrier layer, and a gas-tight, nonporous palladium-bearing separative layer, directing the flowing stream of molten salt into contact with the palladium-bearing layer so that tritium contained within the molten salt is transported through the tritium-separating membrane structure, and contacting a sweep gas with the porous support for collecting the tritium.

Abstract: A getter pump is described. The getter pump has a casing and a getter cartridge mounted within the casing. Each cartridge has a linear central support and spaced getter elements mounted on the linear central support. Each cartridge is positioned along a plane orthogonal to the revolution axis and intersecting the midpoint of a linear central support. The angle formed by each positioning plane with its respective linear central support is comprised between 35° and 75°.

Abstract: A post-accident fission product removal system may include an air mover, a filter assembly, and/or an ionization chamber. The air mover may be configured to move contaminated air through the filter assembly to produce filtered air. The ionization chamber may be connected to the filter assembly. The ionization chamber may include an anode and a cathode. The ionization chamber may be configured to receive the filtered air from the filter assembly and to ionize and capture radioisotopes from the filtered air to produce clean air.

Abstract: A radioisotope generator system may comprise a common platform convertor having two ends, and multiple heat source modules thermally coupled to each other and to the common platform convertor. A portion of the multiple heat source modules may be thermally coupled to each end of the common platform convertor. The common platform convertor may be optimized for a nominal power level.

Abstract: An assembly and to a device for obtaining monochromatic neutron radiation is provided. In order to realize a nuclear synthesis reaction, a starting material is introduced into a pressure booster (gas multiplier) and compressed to the pressure at which the synthesis reaction begins. The resulting neutron radiation passes through the seals of the multiplier elements and an outlet channel in the plug of the pressure chamber (gasostat) vessel, then onto a monochromator and further onto the irradiated object.

Abstract: A Stirling radioisotope generator is provided. The generator includes a first and second heat source assembly, each heat source assembly comprising two General Purpose Heat Source modules, each General Purpose Heat Source module configured to generate thermal energy. The generator also includes a first and second Stirling convertor in thermal communication with the first and second heat source assembly, respectively, each Stirling convertor configured to convert the thermal energy into electrical power. The generator has a housing enclosing the first and second heat source assembly and the first and second Stirling convertor, the housing configured to dissipate excess thermal energy.

Abstract: Technical problems: increasing and regulating the power obtained according to a method and by an apparatus based on nuclear reactions between hydrogen (31) and a primary material (19) comprising cluster nanostructures (21) of a transition metal, in which hydrogen is kept in contact with the clusters (21) within a generation chamber, at a determined process temperature, and in which a process comprising an orbital capture reaction of H? ions (35) by clusters (21) and then a capture reaction by the atoms (38) of the cluster (21) is triggered by impulsively acting on the primary material (19), thus generating an energy as a primary reaction heat (Q1).

Abstract: In accordance with embodiments disclosed herein, there are provided systems, apparatuses and methods for the implementation of an energy system. A mechanical fusion energy system using uniquely constructed fuel pellets containing a variety of fusion capable materials to achieve up to many Megawatts of relatively continuous power output. The disclosed energy system utilizes a quantum approach of individual discrete pops periodically as needed to maintain a fairly continuous flow of energy. It may generate several thousand KWhr of energy per pop and dependent on the pop rate may generate well over 1,000 Megawatts, equivalent to the largest power generating stations currently in operation.

Abstract: Disclosed is a drift tube formed of a hollow cylindrical conductive element having a having an inner surface and a pair of ends. A periodic grating surface is formed on the inner surface of the hollow cylindrical element and the ends are radiused to minimize electrical stress buildup. The interaction between a relativistic electron beam from an electron source passing through the inner space of the hollow element and the internal grating produces RF radiation by the Smith-Purcell Effect. Spacing, face angle and shape of the grating, and the energy of the electron bean are determinants of the frequency of the RF radiation.

Abstract: A method of removing a debris cloud from a fusion reactor includes injecting a fluid jet into the fusion reactor at a first velocity and thereafter, injecting a fusion target into the fusion reactor at a second velocity. The method also includes irradiating the fusion target with laser light and creating a fusion event. The method further includes forming a debris cloud in a vicinity of the fusion event and removing the debris cloud from the fusion reactor. The fluid jet applies a motive force to the debris cloud.

Abstract: This invention combines minor, but not obvious, adaptations of available and, for this field, relatively simple hardware that primarily uses the least power-hungry electrostatic (rather than mainly magnetic) control of accelerated colliding beams of bare deuterium nuclei in three-dimensionally pre-determined collision attitudes that are now found by new research to offer a method (with required apparatus) of fusing directly to helium four with high efficiency release of the greatest possible single-step free energy of fusion in kinetic energy of helium four charged nuclei and with minimized side-effects (if any) of wasted energy and troublesome output products in neutrons, radiation, helium three or tritium nuclei, and plasma electrons. This invention can be combined with the most efficient prior art in deuterium ion sources, continued fusion processes, output power conversion, and full reactor assembly at any scale from laboratory experiments to industrial power networks.

Abstract: A laser inertial-confinement fusion-fission energy power plant is described. The fusion-fission hybrid system uses inertial confinement fusion to produce neutrons from a fusion reaction of deuterium and tritium. The fusion neutrons drive a sub-critical blanket of fissile or fertile fuel. A coolant circulated through the fuel extracts heat from the fuel that is used to generate electricity. The inertial confinement fusion reaction can be implemented using central hot spot or fast ignition fusion, and direct or indirect drive. The fusion neutrons result in ultra-deep burn-up of the fuel in the fission blanket, thus enabling the burning of nuclear waste. Fuels include depleted uranium, natural uranium, enriched uranium, spent nuclear fuel, thorium, and weapons grade plutonium. LIFE engines can meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the highly undesirable stockpiles of depleted uranium, spent nuclear fuel and excess weapons materials.

Abstract: An apparatus for generating power includes a cage having a plurality of elongated elements defining a space within the cage, wherein the space has a region for allowing ion collision to occur, and a pair of electromagnets located at or near respective opposite ends of the cage. An apparatus for generating power includes a vacuum chamber, a first solenoid, a second solenoid, wherein the first and the second solenoids are located on opposite sides of the vacuum chamber, and a coupler that mechanically couples the first solenoid to the second solenoid, wherein the coupler has an end defining an opening that resembles a dumbbell shape.

Abstract: A method for producing energy from nuclear reactions between hydrogen and a metal, includes a) production of a determined quantity of micro/nanometric clusters of a transition metal, b) bringing hydrogen into contact with the clusters and controlling its pressure and speed; c) creating an active core for the reactions by heating the clusters up to a temperature that is higher than the Debye temperature TD of the metal; d) triggering the reactions by a mechanical, thermal, ultrasonic, electric or magnetic impulse on the active core, causing the atoms of the metal to capture the hydrogen ions, with liberation of heat; and e)removing the heat maintaining the temperature above TD.

Abstract: A practical technique for inducing and controlling the fusion of nuclei within a solid lattice. A reactor includes a loading source to provide the light nuclei which are to be fused, a lattice which can absorb the light nuclei, a source of phonon energy, and a control mechanism to start and stop stimulation of phonon energy and/or the loading of reactants. The lattice transmits phonon energy sufficient to affect electron-nucleus collapse. By controlling the stimulation of phonon energy and controlling the loading of light nuclei into the lattice, energy released by the fusion reactions is allowed to dissipate before it builds to the point that it causes destruction of the reaction lattice.

Abstract: Disclosed herein are embodiments of systems and methods for creating tracer nuclear materials. In one aspect, a Compact Fusion Neutron Source (CFNS) as described herein, can be used to create tracer isotopes to be added to fissile fuels to aid in anti-proliferation, though other methods of creating isotopes are contemplated. The generation of the isotopes require (n,2n) reactions, which can be caused by the high energy neutrons created by fusion. Potential tracer isotopes include U232, Th228 and Pu236, although other isotopes may be used. Such tracer isotopes can be created (such as by a CFNS), and then added to fissile materials at some stage of their processing. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

Abstract: A system for forming a thick flowing liquid metal, in this case lithium, layer on the inside wall of a toroid containing the plasma of a deuterium-tritium fusion reactor. The presence of the liquid metal layer or first wall serves to prevent neutron damage to the walls of the toroid. A poloidal current in the liquid metal layer is oriented so that it flows in the same direction as the current in a series of external magnets used to confine the plasma. This current alignment results in the liquid metal being forced against the wall of the toroid. After the liquid metal exits the toroid it is pumped to a heat extraction and power conversion device prior to being reentering the toroid.

Abstract: Featured is a plasma extrusion dynamo and methods related thereto. Also featured are fusion reactors using such dynamos and methods. In the methodology of the present invention, a steady-state stream of conductive plasma is forced by pressure or momentum to flow into a magnetic extrusion nozzle made up of converging magnetic field lines so as to form a closed, steady-state current loop within the plasma. The plasma current loop in turn forms a closed set of poloidal field lines which interact with the plasma current to compress and confine a portion of the plasma in a toroidal volume. Such pressure and confinement establish the conditions for magnetically confining controlled nuclear fusion reactions for power generation. A fusion reactor using the plasma extrusion dynamo methodology includes a source of high pressure or high velocity plasma, one or more converging magnetic extrusion nozzles, and a plasma exhaust area at low pressure.

Abstract: Substantially spherical particles of lithium silicates with improved mechanical properties and improved surface quality are provided, which are particularly suited for use as breeding material for tritium. The particles are characterised in that they contain additions of tellurium and/or tellurium compounds.

Abstract: A novel hydrogen ion array acceleration generator and method are presented wherein there is provided along a transversely extending diffusion/emission grid surface and within an evacuated contained environment, an array of hydrogen ions at the interstitial sites of the grid surface; such being electrically accelerated along a longitudinal direction substantially normal to said surface toward a transversely extending lattice surface of a heavy metal of atomic radius between about 1.23 and 1.

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

Abstract: Substantially spherical particles of lithium silicates with improved mechanical properties and improved surface quality are provided, which are particularly suited for use as breeding material for tritium. The particles are characterized in that they contain additions of tellurium and/or tellurium compounds.

Abstract: Optical paths of laser beams generated from at least two laser beam generators, which are used for performing connection and cutting work at prescribed locations of structural members, are each switched by corresponding optical path switchers, and the laser beams polarized by the corresponding optical path switchers are reflected in the same direction by a laser beam combiner to combine the plurality of laser beams into a parallel laser beam bundle, in order to perform cutting or welding at the corresponding prescribed location. This configuration removes the need to provide high-power laser beam generators for situations such as vacuum walls of fusion devices where the laser generation efficiency is low, while also making it possible to use more powerful high-power lasers therein if necessary.

Abstract: A fusion reactor has an internal component in which an internal structure assembly is housed in a toric vacuum vessel in an arrangement along a circumferential direction thereof and in which a high-temperature plasma in which hydrogen and hydrogen isotopes are maintained in a plasma state is confined in a toric internal space defined in the internal structure assembly. The internal component includes a cooling structure of a multi-wall structure having multiple walls formed to the internal structure assembly and a flow channel formed in the cooling structure for a cooling fluid for extracting heat caused by plasma and a nuclear reaction.

Abstract: A ceramic catalytic membrane reactor for the separation of hydrogen and/or isotopes thereof from fluid, in particular gaseous flows, formed of a tubular support (1) made of a porous ceramic material, which is coated with layers (4) of a gas-tight material at both ends thereof, and with a thin layer or film (2) of a metal or metal alloy having catalytic activity and selective permeability to hydrogen and isotopes thereof, such as Pd or Pd/Ag, on a central portion thereof, where the reaction takes place. The central portion is provided with heating. The seals (6) of the membrane reactor are located on the two gas-tight ends of the tubular support (1).

Abstract: The process for containing a deuterium gas plasma discharge includes providing a cylindrical zone having a cylinder axis; supplying D.sub.

Abstract: The heat shield according to the invention makes it possible to protect a structure from a very high thermal flux. It is mainly constituted by tiles (2) fixed to a support structure (4) by means of a spring (8) fixed in translation with respect to a tile (2) and on which bears a locking arm (10). The latter can be fixed to the support structure (4) by means of locking screws (30), which are accessible from the outside through locking orifices (12) in the tile (2). The compression of the spring (8) allows locking to take place and also a satisfactory heat exchange from the tile (2) to the support structure (4), which can be cooled by cooling medium flow ducts (14).

Abstract: An approach (10) is provided as a way of obtaining useful power from a fusion reaction utilizing light weight isotopes of hydrogen and helium. A potential well is created between two accelerating electrodes (26) that, in a vacuum, allows ions from sources (24) to be captured by the potential well. An axial magnetic field as created by solenoid (20) causes the captured ions to pass through an ion focusing region (22) and thus allowing fusion reactions to take place within the region. The magnetic field also confines the trajectory of the fusion products (18) to a series of helixes preventing them from reaching the solenoid walls, but instead forces them to exit the two ends of the solenoid. Useful power is obtained by allowing two heat exchangers to intercept the fusion ions and thereby allowing a coolant liquid to be heated as would be required to operate a steam turbogenerator.

Abstract: Fusion reactor (36) based on the cusped geometry concept in which the problem of indefinite tight plasma containment with inherent stability and high compression of the contained plasma in the reaction zone (19) is solved by an electric potential pot (22) surrounding the reaction zone and having an ion source (37) at the upper potential pot edge (38).

Abstract: The invention provides a new high temperature isotopic exchange fuel processing loop for tritium recovery in which tritium is exchanged out of impurities such as tritiated ammonia, methane and water by swamping with H.sub.2 and isotopically equilibrating the mixture in a high temperature reactor. Downstream of the reactor is a Pd/Ag permeator for separation of the hydrogen from the impurities, the separated hydrogen being sent to an isotope separation system for tritium recovery and the residual impurities being recycled. The process eliminates the need for impurity oxidation and electrolysis of DTO and does not rely on complicated catalytic decomposition reactions.

Abstract: This invention relates to adaptation of intersecting storage rings, of the same type used in high energy nuclear physics research, for power generation. The device is optimized for lower-energy beam paricles and higher beam current, adapted with a reaction chamber at the intersection of the rings to collect released fusion energy for conversion to electricity, and equipped with means to recapture scattered accelerated particles and reintegrate them into the focused beams for recirculation through the reaction chamber. The preferred beam particles, deuterium and tritium, are accelerated and injected into and focused by the storage rings, to collide nearly head on in the reaction chamber. Non-colliding, accelerated beam particles are conserved by recovery, correction and recirculation, requiring relatively small amounts of input energy to maintain acceleration and focus of the beams, and thus remain energized for another collision attempt.

Abstract: An apparatus is provided for driving a solid state laser by a nuclear powered fluorescence source which is located remote from the fluorescence source. A nuclear reaction produced in a reaction chamber generates fluorescence or photons. The photons are collected from the chamber into a waveguide, such as a fiber optic waveguide. The waveguide transports the photons to the remote laser for exciting the laser.

Abstract: A reactor for use in the separation of tritium from tritiated water by the vapor phase catalytic exchange process comprises an evaporator section, a superheater section, a catalytic reactor section and a condenser section serially arranged within a common casing structure defining a unitary pressure vessel. In a multistage plant the reactors are interconnected to provide for countercurrent flow of the water and hydrogen gas from stage to stage, with co-current contact in the catalytic reactor section of each stage. By incorporating the components of each stage in a common casing structure, the external piping is minimized and the risk of leakage is reduced.

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

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

Abstract: Accelerated decay of radioactive materials is used for power production. In the method of this invention an alpha-emitting radioactive material is placed in a region. The region is selected so that when a negative potential is applied to the region, enhanced alpha decay of the radioactive material results. The energy of the alpha decay particles is captured and converted to thermal energy.

Abstract: An atmospheric tritium sampler is provided which uses a carrier gas comprised of hydrogen gas and a diluting gas, mixed in a nonexplosive concentration. Sample air and carrier gas are drawn into and mixed in a manifold. A regulator meters the carrier gas flow to the manifold. The air sample/carrier gas mixture is pulled through a first moisture trap which adsorbs water from the air sample. The mixture then passes through a combustion chamber where hydrogen gas in the form of H.sub.2 or HT is combusted into water. The manufactured water is transported by the air stream to a second moisture trap where it is adsorbed. The air is then discharged back into the atmosphere by means of a pump.

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

Abstract: Method for extending service life of nuclear reactor components prepared from ductile, high strength crystalline alloys obtained by devitrification of metallic glasses. Two variations of the method are described: (1) cycling the temperature of the nuclear reactor between the operating temperature which leads to irradiation damage and a lThe U.S. Government has rights in this invention by virtue of Department of Energy, Office of Fusion Energy, Grant No. DE-AC02-78ER-10107.

Abstract: The exhaust gas of a fusion reactor contains, besides non-burnt fuel (tritium and deuterium) and helium, the "ash" from the nuclear fusion reaction a number of impurities with the radioactive tritium and/or deuterium chemically bound to them. In order to clean the exhaust gas, both the elemental and the chemically bound tritium and/or deuterium fractions are separated from the exhaust gas. Separation is achieved exclusively by physical and catalytical process steps, namely a palladium/silver permeator, a CuO/Cr.sub.2 O.sub.3 /ZnO catalyst bed and a further palladium/silver permeator containing a nickel/aluminum oxide bulk catalyst.

Abstract: An apparatus and method for reacting on material by means of intense radiation employed to change the physical and, in certain instances, the chemical characteristics of such material. In one form, an intense radiation beam is directed into a cavity of a die or support for a small quantity of material to be reacted on and the intense heat of the beam as well as the shock wave generated in the material in the die cavity by the rapid heat of the beam react on such material to change its physical characteristics. In another form, two or more intense radiation beams, such as generated by one or more lasers or electron guns as intense pulses of radiation, are directed against a particle or pellet of material directed along a predetermined path into a reaction chamber, intensely heat and transmit shock wave energy thereto from opposite directions which shock waves collapse against the material transforming it into another form.

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