Abstract: A nested pebble bed blanket surrounds a fusion reactor's vacuum chamber. The blanket includes stacks of nested pebbles composed of neutron multiplier shells filled with breeding spheroids. The shells have perforations passing through their inner and outer surfaces. The shells include therein perforated coolant distributor elements coupled to or unitary with the inner surfaces. Each perforated element is in line with a respective shell perforation, which allows coolant to flow into the sphere through the perforations and elements. When bombarded by neutrons, the nested pebbles produce fusion fuel to sustain fusion reactions. The coolant sweeps out the fusion fuel, and cools the breeding spheroids. Pebbles in the blanket are replenished with conveyor systems. A separator extracts the fusion fuel from the blanket coolant. Heat from the walls and the nested pebble bed is extracted by inert gases and then conveyed to a thermal storage and/or a power cycle.

Abstract: Provided herein are high energy ion beam generator systems and methods that provide low cost, high performance, robust, consistent, uniform, low gas consumption and high current/high-moderate voltage generation of neutrons and protons. Such systems and methods find use for the commercial-scale generation of neutrons and protons for a wide variety of research, medical, security, and industrial processes.

Abstract: The invention provides methods and apparatus for extracting ions, and further for producing neutrons from the extracted ions. In an aspect, there is provided a method for extracting ions involving the following step: in a vacuum chamber applying voltages to a spark gap between two electrodes comprising coatings of a hydrocarbon, each voltage sufficient to trigger a spark discharge in the gap sufficient to dissociate the hydrocarbon and extract therefrom hydrogen ions, wherein the hydrocarbon is a nonvolatile liquid sufficiently non-viscous to flow and re-coat holes in the coatings between each spark discharge.

Abstract: A fusion reactor includes a columnating panel disposed between the positive electrode and negative electrode for channeling deuterium ions along predetermined paths that are likely to lead to fusion-producing collisions with previous deuterium ions. Deuterium ions are introduced to the reactor adjacent to the positive electrode, and then pass from the columnating panel, through a reduced pressure chamber, and then proceed towards the negative electrode. Once the deuterium ions strike the negative electrode, they remain attached to the negative electrode so that subsequent deuterium ions following the same channels through the columnating panel are more likely to collide with them.

Abstract: An ion source for use in a radiation generator tube includes a back passive cathode electrode, a passive anode electrode downstream of the back passive cathode electrode, a magnet adjacent the passive anode electrode, and a front passive cathode electrode downstream of the passive anode electrode. The front passive cathode electrode and the back passive cathode electrode define an ionization region therebetween. At least one ohmically heated cathode is configured to emit electrons into the ionization region. The back passive cathode electrode and the passive anode electrode, and the front passive cathode electrode and the passive anode electrode, have respective voltage differences therebetween, and the magnet generating a magnetic field, such that a Penning-type trap is produced to confine the electrons to the ionization region. At least some of the electrons in the ionization region interact with an ionizable gas to create ions.

Abstract: An ion source for use in a radiation generator tube includes a back passive cathode electrode, a passive anode electrode downstream of the back passive cathode electrode, a magnet adjacent the anode, and a front passive cathode electrode downstream of the passive anode electrode. The front passive cathode electrode and the back passive cathode electrode define an ionization region therebetween. At least one field emitter array (FEA) cathode is configured to electrostatically discharge due to an electric field in the ion source. The back passive cathode electrode and the passive anode electrode, and the front passive cathode electrode and the passive anode electrode, have respective voltage differences therebetween, and the magnet generating a magnetic field, such that a Penning-type trap is produced to confine electrons from the electrostatic discharge to the ionization region. At least some of the electrons in the ionization region interact with an ionizable gas to create ions.

Abstract: A neutron generator includes an ion source disposed in a pressurized environment containing an ionizable gas. The ion source includes a substrate with a bundle of carbon nanotubes extending therefrom. The ends of the nanotubes are spaced from a grid. Ion source voltage supply circuitry supplies a positive voltage potential between the substrate and the grid of the ion source to cause ionization of the ionizable gas and emission of ions through the grid. An ion accelerator section is disposed between the ion source and a target. The ion accelerator section accelerates ions that pass through the grid towards the target such that collisions of the ions with the target cause the target to generate and emit neutrons therefrom. The ion source, accelerator section and target are housed in a sealed tube and preferably the carbon nanotubes of the bundle are highly ordered with at least 106 carbon nanotubes per cm2 that extend in a direction substantially parallel to the central axis of the tube.

Abstract: Aspects of the invention relate to several methods to deposit and regenerate target materials in neutron generators and similar nuclear reaction devices. In situ deposition and regeneration of a target material reduces tube degradation of the nuclear reaction device and covers impurities on the surface of the target material at the target location. Further aspects of the invention include a method of designing a target to generate neutrons at a high efficiency rate and at a selected neutron energy from a neutron energy spectrum.

Abstract: A method is provided for producing neutrons, comprising: providing a converter foil comprising deuterium clusters; focusing a laser on the foil with power and energy sufficient to cause deuteron ions to separate from the foil; and striking a surface of a target with the deuteron ions from the converter foil with energy sufficient to cause neutron production by a reaction selected from the group consisting of D-D fusion, D-T fusion, D-metal nuclear spallation, and p-metal. A further method is provided for assembling a plurality of target assemblies for a target injector to be used in the previously mentioned manner. A further method is provided for producing neutrons, comprising: splitting a laser beam into a first beam and a second beam; striking a first surface of a target with the first beam, and an opposite second surface of the target with the second beam with energy sufficient to cause neutron production.

Abstract: A thermonuclear reaction system for generating a thermonuclear fusion reaction includes a reaction chamber and a number of particle beam emitters. The particle beam emitters are supported spatially around oriented toward a common focal region of the reaction chamber. The particle beam emitters accelerate energized particles of at least one thermonuclear fuel type, such as hydrogen or deuterium, into the reaction chamber as a plurality of particle beams converging at the common focal region. When the high-energy particle beams converge at the common focal region, the resulting plasma ball is sufficiently dense and hot that a thermonuclear fusion reaction is instigated and thereafter sustained by the energy release accompanying the fusion reactions. Optionally, laser beams or other input energy devices may also be oriented around and toward the common focal region to direct high-energy laser beams at the plasma ball to assist with instigation of the fusion reaction.

Abstract: Aspects of the invention relate to several methods to deposit and regenerate target materials in neutron generators and similar nuclear reaction devices. In situ deposition and regeneration of a target material reduces tube degradation of the nuclear reaction device and covers impurities on the surface of the target material at the target location. Further aspects of the invention include a method of designing a target to generate neutrons at a high efficiency rate and at a selected neutron energy from a neutron energy spectrum.

Abstract: A cylindrical neutron generator is formed with a coaxial RF-driven plasma ion source and target. A deuterium (or deuterium and tritium) plasma is produced by RF excitation in a cylindrical plasma ion generator using an RF antenna. A cylindrical neutron generating target is coaxial with the ion generator, separated by plasma and extraction electrodes which contain many slots. The plasma generator emanates ions radially over 360° and the cylindrical target is thus irradiated by ions over its entire circumference. The plasma generator and target may be as long as desired. The plasma generator may be in the center and the neutron target on the outside, or the plasma generator may be on the outside and the target on the inside. In a nested configuration, several concentric targets and plasma generating regions are nested to increase the neutron flux.

Abstract: Described herein are integrated systems for generating neutrons to perform a variety of tasks including: on-line analysis of bulk material and industrial process control (as shown in FIG. 1), security interrogation (as shown in FIG. 2), soil and environmental analysis, and medical diagnostic treatment. These systems are based on novel gas-target neutron generation which embodies the beneficial characteristics of replenishable fusible gas targets for very long lifetime, stability and continuous operation, combined with the advantageous features common to conventional accelerator neutron tubes including: on/off operation, hermetically sealed operation, and safe storage and transport. Innovative electron management techniques provide gas-target neutron production efficiencies that are comparable or surpass existing sources.

Abstract: A method of producing an isotope comprising directing electrons at a converting material coated with a coating material, the coating material having an atomic number of n, whereby interaction of the electrons with the converting material produces photons, and whereby the photons produced interact with the coating material to produce an isotope having an atomic number of n−1. In preferred embodiments, the converting material is Tungsten, the coating material having an atomic number of n is Radium-226, and the isotope having an atomic number of n−1 is Radium-225.

Abstract: Described herein are integrated systems for generating neutrons to perform a variety of tasks including: on-line analysis of bulk material and industrial process control (as shown in FIG. 1), security interrogation (as shown in FIG. 2), soil and environmental analysis, and medical diagnostic treatment. These systems are based on novel gas-target neutron generation which embodies the beneficial characteristics of replenishable fusible gas targets for very long lifetime, stability and continuous operation, combined with the advantageous features common to conventional accelerator neutron tubes including: on/off operation, hermetically sealed operation, and safe storage and transport. Innovative electron management techniques provide gas-target neutron production efficiencies that are comparable or surpass existing sources.

Abstract: Flow of mercury from a liquid-heavy-metal inflow port toward an inner forward end of a container body is rectified by a plurality of incoming-passage guide vanes in a liquid-heavy-metal incoming passage. Flow of the mercury from the forward end of the container body toward a liquid-heavy-metal outflow port is rectified by a plurality of return-passage guide vanes in a liquid-heavy-metal return passage. As a result, occurrence of stagnation and/or recirculation flows of the mercury in the container body is suppressed and a steady and highly uniform stream of the mercury is formed throughout in the container body. The container body is covered with a container outer shell to prevent any leakage of the mercury to outside due to a damage of the container body.

Abstract: A device for reconditioning a neutron tube, comprising on the one hand invariant elements and on the other hand sensitive elements which are subject to wear and gaseous elements which are consumable and which are introduced by way of reservoirs. In accordance with the invention the sensitive elements, for example target (6) and gas reservoirs (7, 8) are collected in the same part (1') of the tube, which part is separable from the other part (1) by means of a tight connection system (12, 12', 13, 14 and 15) in order to make the replacements necessary for reconditioning.

Abstract: A neutron generator comprising a target (16) which is struck by a hydrogen isotope ion beam and which is formed by a structure comprising a thin absorbing active layer (19) deposited on a carrier layer (18). In accordance with the invention, on the two above layers there is deposited a stack of active layers (21, 23, 25, 27) which are identical to the layer (19) and which are separated from one another by diffusion barriers (20, 22, 24, 26, respectively). The thickness of each of said active layers is in the order of the penetration depth of the deuterium ions striking the target.

Abstract: A nuclear fusion device comprising a condensed phase fuel element and accelerated ion beams which ionize and compress the fuel element and initiate nuclear fusion reactions. In one of the embodiment beams comprising electrons in addition to ions are employed. A method is provided comprising synchronization, acceleration and focusing of the said beams on the fuel target. Another object of the invention is to provide an apparatus and method for a continuous nuclear fusion process. Another object is a clean fusion process. A further object of the invention is to provide a neutron generator.

Abstract: A control and power supply circuit is illustrated in the preferred and illustrated embodiment for providing power to a pulsed neutron generator tube. The preferred and illustrated embodiment includes power supplies and control circuits for providing operative power to the pulsed neutron generator tube. The system monitors the voltages supplied to a downhole sonde utilizing a shut regulator circuit which, with the remainder of the control circuitry set forth, properly and in controlled sequence empowers the pulsed neutron generator tube. The tube is provided with power to switch on and such power is switched off in timed sequence to avoid damaging the tube in the event of a malfunction or loss of power from the surface located power source for the sonde.

Abstract: An intense high current, high voltage pulsed beam comprising bursts of electrons of about 40 nanoseconds duration each, having a beam radius of about 1 mm is projected through an anode consisting of a hollow tube with much smaller diameter than that of the diode tube surrounding the cathode. By appropriate selection of combinations of materials, sizes, shapes, and surface treatments surrounding the beam in its travel through the anode, or by means such as ion beams directed back along the beam, or by laser pulses on selected areas inside the anode or on the cathode tip, or by controlling supply of appropriate gases or vapors through a small diameter tubular cathode, either metallic or dielectric, and separately into the tubular anode near the end farthest from the cathode and nearer the target, the beam is made to pinch down to a radius of about 0.

Abstract: The ion accelerator comprises an arrangement consisting of getter pumps and gas storages. This makes for a possibility of gas pressure and gas phase composition control in the device after its being unsoldered from the vacuum installation. The device is equipped with an evaporator and an additional gas storage which permit renovating the target surface as required. Proposed herein is a method ensuring higher efficiency of the device operation.

Abstract: A neutron accelerator tube having a replenisher section for supplying accelerator gas, in ionization section adjacent the replenisher section adapted to receive the accelerator gas, and a target section adjacent the ionization section. The target section includes a chamber having a tritium target therein. A cathode member is interposed between the ionization section and the target chamber and has a recessed convergent surface exposed to the target chamber. An aperture in the cathode member at the vortex of this recessed surface provides for the extraction of ionized accelerator gas from the ionization section into the target chamber. An extraction electrode is also located in the target chamber between the target and the cathode and has a divergent projecting surface facing the recessed cathode surface. This electrode has an aperture at the apex of the projecting surface through which ionized accelerator gas may may be directed at the target.