Abstract: Provided herein are systems, devices, articles of manufacture, and methods for generating neutrons employing a high energy ion beam target (HEM target) and a target backing configured to be in contact with the bottom surface of the HEIB target (e.g., to generate an ion beam target assembly). In certain embodiments, the HEM target has a thickness that is less than the penetration depth of protons or deuterons in the high energy ion beam that strikes the target. In certain embodiments, the target backing comprises a high hydrogen diffusion metal (e.g., palladium), has open spaces dispersed throughout for reduced proton diffusion distances, and has a shape and thickness such that all, or virtually all, of the protons or deuterons that pass through the HEIB target are stopped. Also provided herein are systems, devices, and methods for changing targets in an ion beam accelerator system.

Abstract: A neutron capture therapy system includes an accelerator for accelerating charged particles to generate a charged particle beam, a beam transmitting device, and a neutron beam generating device. The neutron beam generating device further includes a first, a second and a third neutron beam generating device. The beam transmitting device further includes a first transmitting device connected to the accelerator, a beam direction conversion device configured to switch a traveling direction of the charged particle beam, and a second, a third and a fourth transmitting device that respectively transmit the charged particle beam from the beam direction conversion device to the first, the second and the third neutron beam generating device, wherein two of the first, the third and the fourth transmitting device define a first plane, a first and a second transmitting device define a second plane, and the first plane is different from the second plane.

Abstract: A capsule for the transfer of a target material in a conveying system between a target irradiation station and a collecting station comprising: a beamline channel for the passage of an energetic beam irradiating the target material, a target holder holding the target material or a substrate backing the target material at a glancing angle with respect to the beamline channel axis, a degrader foil positioned across the beamline channel for degrading an energy of the energetic beam upstream of the target material, a target cooling inlet and a target cooling outlet for passage of a cooling fluid in a target cooling duct in a vicinity of the target holder such that the target material can be cooled during an irradiation, and a degrader foil cooling inlet and a degrader foil cooling outlet for passage of a cooling gas in a vicinity of the degrader foil.

Abstract: Provided is a target plate for radioisotope production that has sufficient durability and sufficient heat resistance for use in radioisotope production and that is capable of reducing the extent of radioactivation. In a target plate for radioisotope production, a support substrate, which supports a target, includes a graphite film(s). The thermal conductivity in a surface direction of the graphite film(s) is 1200 W/(m·K) or greater, and the thickness of the graphite film(s) is 0.05 ?m or greater and 100 ?m or less.

Abstract: Conventional cyclotrons have been incapable of changing energy of a beam to be extracted. Conventional synchrotrons have been difficult to output beams in a continuous manner. An accelerator has a dense region dense region in which orbits of different energies densely gather as a result of using a radiofrequency electric field to accelerate an ion orbiting in an isochronous magnetic field in order to cause a beam orbit to be displaced in a specific direction with increasing acceleration, and a sparse region in which orbits of different energies are sparsely discrete from each other. The accelerator has a feature that a magnetic field has a magnetic field gradient in a radial direction of a beam orbit in the dense region, and a product of a gradient of magnetic field gradient and a beam size passing through the dense region becomes smaller than the magnetic field gradient.

Abstract: Target assembly for an isotope production system. The target assembly includes a target body having a production chamber and a beam cavity that is adjacent to the production chamber. The production chamber is configured to hold a target liquid. The beam cavity opens to an exterior of the target body and is configured to receive a particle beam that is incident on the production chamber. The target assembly also includes a vibrating device that is secured to the target body. The vibrating device is configured to cause vibrations that are experienced within the production chamber.

Abstract: The invention relates to an arrangement for producing a proton beam. This arrangement is characterized in that it is constituted by a laser driven accelerator of protons adapted to produce a beam of relativistic protons of 0.5 GeV to 1 GeV with a current in the order of tens of mA, such as a current of 20 mA. The invention can be used for transmutating nuclear waste.

Abstract: The invention relates to a device (1) for producing radioisotopes by irradiating a target fluid using a particle beam (13). This device comprises an irradiation cell (7) that includes a cavity (3) for receiving the target fluid. A non-cryogenic cooling device cools the walls of the cavity (3). The cavity (3) has an inclined surface (15) downwardly delimiting the cavity (3) so as to evacuate the target fluid, which condenses on contact with the cooled walls, under gravity towards a metal foil (4) which closes off this cavity (3). The inclined surface (15) intersects the plane formed by the metal foil (4), making an acute angle (a) with said plane, so as to form with the metal foil (4) a wedge-shaped zone (18) capable of collecting, by gravity, the condensed target fluid.

Abstract: An apparatus for generating x-rays includes an electron beam generator and a first device arranged to apply an RF electric field to accelerate the electron beam from the generator. A photon source is arranged to provide photons to a zone to interact with the electron beam from the first device so as to generate x-rays via inverse-Compton scattering. A second device is arranged to apply an RF electric field to decelerate the electron beam after it has interacted. The first and second devices are connected by RF energy transmission means arranged to recover RF energy from the decelerated electron beam as it passes through the second device and transfer the recovered RF energy into the first device.

Abstract: Systems and methods for operating an accelerator driven sub-critical core. In one embodiment, a fission power generator includes a sub-critical core and a plurality of proton beam generators. Each of the proton beam generators is configured to concurrently provide a proton beam into a different area of the sub-critical core. Each proton beam scatters neutrons within the sub-critical core. The plurality of proton beam generators provides aggregate power to the sub-critical core, via the proton beams, to scatter neutrons sufficient to initiate fission in the sub-critical core.

Abstract: The invention provides a compact high energy proton source useful for medical isotope production and for other applications including transmutation of nuclear waste. The invention further provides a device that can be used to generate high fluxes of isotropic neutrons by changing fuel types. The invention further provides an apparatus for the generation of isotopes including but not limited to 18F, 11C, 15O, 63Zn, 124I, 133Xe, 111In, 125I, 131I, 99Mo, and 13N.

Abstract: The present invention provides a method for producing molybdenum-99 comprising: i) providing an electron accelerator; ii) providing a molybdenum converter/target unit (Mo-CTU) comprising one or more metallic components, wherein each one of said metallic components is made of a material selected from the group consisting of natural molybdenum, molybdenum-100, molybdenum-98, and mixtures thereof; iii) directing an electron beam generated via said electron accelerator onto said Mo-CTU to produce a braking radiation (bremsstrahlung); iv) employing said bremsstrahlung onto said Mo-CTU to produce molybdenum-99 and neutrons via a photo-neutron reaction; v) slowing down the neutrons produced in step iv) with a low atomic liquid, e.g. distilled water; and optionally vi) employing the neutrons produced in step iv) to produce a complementary amount of molybdenum-99 via a neutron capture reaction on said Mo-CTU. The invention further provides an apparatus for producing molybdenum-99.

Abstract: Biomass (e.g., plant biomass, animal biomass, and municipal waste biomass) is processed to produce useful products, such as fuels. For example, systems can use feedstock materials, such as cellulosic and/or lignocellulosic materials and/or starchy materials, to produce ethanol and/or butanol, e.g., by fermentation.

Abstract: Biomass (e.g., plant biomass, animal biomass, and municipal waste biomass) is processed to produce useful products, such as fuels. For example, systems can use feedstock materials, such as cellulosic and/or lignocellulosic materials and/or starchy materials, to produce ethanol and/or butanol, e.g., by fermentation.

Abstract: An ion source includes a conductive substrate, the substrate including a plurality of conductive nanostructures with free-standing tips formed on the substrate. A conductive catalytic coating is formed on the nanostructures and substrate for dissociation of a molecular species into an atomic species, the molecular species being brought in contact with the catalytic coating. A target electrode placed apart from the substrate, the target electrode being biased relative to the substrate with a first bias voltage to ionize the atomic species in proximity to the free-standing tips and attract the ionized atomic species from the substrate in the direction of the target electrode.

Abstract: One embodiment of the present invention includes a process for production and recovery of no-carrier-added radioactive tin (NCA radiotin). An antimony target can be irradiated with a beam of accelerated particles forming NCA radiotin, followed by separation of the NCA radiotin from the irradiated target. The target is metallic Sb in a hermetically sealed shell. The shell can be graphite, molybdenum, or stainless steel. The irradiated target can be removed from the shell by chemical or mechanical means, and dissolved in an acidic solution. Sb can be removed from the dissolved irradiated target by extraction. NCA radiotin can be separated from the remaining Sb and other impurities using chromatography on silica gel sorbent. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

Abstract: A particle beam target for producing radionuclides includes a target body, a target cavity, parallel grooves, peripheral bores, and radial outflow bores. The parallel grooves are formed in a back side of the target body and include respective first and second groove ends. The peripheral bores extend through the target body from the plurality of grooves generally toward the front side that receives a particle beam. Each groove communicates with a peripheral bore at the first groove end and another peripheral bore at the second groove end. The radial outflow bores extend radially from the plurality of peripheral bores. The target body defines a plurality of liquid coolant flow paths. Each liquid coolant flow path runs from a respective groove to at least one of the first groove end and the second groove end of the respective groove, through at least one peripheral bore, and through at least one radial outflow bore.

Abstract: Apparatus for generating thermal neutrons includes an electron accelerator for generating an electron beam and a converter for converting the electron beam into photons. A receiving device is provided for receiving the photons and includes a material which provides a photoneutron target for the photons, for producing high energy neutrons in a photonuclear reaction between the photons and the photoneutron target, and for moderating the high energy neutrons to generate the thermal neutrons. The electron beam has an energy level high enough to produce photons of sufficient energy to exceed the photodissociation threshold of the selected target material, but that is sufficiently low as to enable the material to moderate the high energy neutrons resulting from the photonuclear reaction.

Abstract: An accelerator pack, specifically for linear accelerator modules cascade-connected to a proton-emitting cyclotron, specially adapted for use in cancer therapies. Such a technique is named PT. The pack displays an accelerating cavity of improved efficiency in virtue of its shape, which provides for making a portion of accelerating cavity on both faces of the pack. Furthermore, the pack also contains a coupling cavity portion. In such a manner, the volume of the accelerating cavity is increased as compared to that of the packs of the known accelerator modules.

Abstract: The invention relates to a device (1) for producing radioisotopes by irradiating a target fluid using a particle beam (13). This device comprises an irradiation cell (7) that includes a cavity (3) for receiving the target fluid. A non-cryogenic cooling device cools the walls of the cavity (3). The cavity (3) has an inclined surface (15) downwardly delimiting the cavity (3) so as to evacuate the target fluid, which condenses on contact with the cooled walls, under gravity towards a metal foil (4) which closes off this cavity (3). The inclined surface (15) intersects the plane formed by the metal foil (4), making an acute angle (a) with said plane, so as to form with the metal foil (4) a wedge-shaped zone (18) capable of collecting, by gravity, the condensed target fluid.

Abstract: Target windows for isotope production systems are provided. One target window includes a plurality of foil members in a stacked arrangement. The foil members have sides, and wherein the side of a least one of the foil members engages the side of at least one of the other foil members. Additionally, at least two of the foil members are formed from different materials.

Abstract: The present invention provides a method for producing Cu67 radioisotope suitable for use in medical applications. The method comprises irradiating a metallic zinc-68 (Zn68) target with a high energy gamma ray beam. After irradiation, the Cu67 is isolated from the Zn68 by any suitable method (e.g., chemical and/or physical separation). In a preferred embodiment, the Cu67 is isolated by sublimation of the zinc (e.g., at about 500-700° C. under reduced pressure) to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means (i.e., dissolution in acid, followed by ion exchange).

Abstract: The present invention relates to an apparatus for producing a radioisotope by irradiating a target fluid comprising a precursor of said radioisotope with a particle beam produced by a particle accelerator, the apparatus comprising:—a housing comprising a target cavity for receiving said target fluid, said housing having an opening for allowing the passage of the said particle beam into the said cavity;—a dual foil flange for closing said opening of the target cavity, said dual foil flange comprising:—a standoff comprising a central hole;—a first and a second foil able to allow the passage of the said particle beam and located respectively on a first side and a second side of the said standoff, covering the said central hole and forming a cooling cavity;—a first flange and a second flange for sealing respectively the said first and second foil on said standoff;—at least an inlet channel and at least an outlet channel, for flowing a cooling fluid through the cavity of the dual foil flange;—guiding means for pos

Abstract: An apparatus for generating medical isotopes provides an annular fissile solution vessel surrounding a neutron generator. The annular fissile solution vessel provides for good capture of the emitted neutrons and a geometry that provides enhanced stability in an aqueous reactor. A neutron multiplier and/or a neutron moderator may be used to improve the efficiency and control the criticality of the reaction in the annular fissile solution vessel.

Abstract: An apparatus for producing thermal or epithermal neutrons in a sample has a plurality of fast neutron sources positioned around a cylindrical or spherical moderator to maximize the neutron flux at a sample placed in a void at the center of the moderator.

Abstract: A method and isotope linac system are provided for producing radio-isotopes and for recovering isotopes. The isotope linac is an energy recovery linac (ERL) with an electron beam being transmitted through an isotope-producing target. The electron beam energy is recollected and re-injected into an accelerating structure. The ERL provides improved efficiency with reduced power requirements and provides improved thermal management of an isotope target and an electron-to-x-ray converter.

Abstract: An isotope production system that includes a cyclotron having a magnet yoke that surrounds an acceleration chamber. The cyclotron is configured to direct a particle beam from the acceleration chamber through the magnet yoke. The isotope production system also includes a target system that is located proximate to the magnet yoke. The target system is configured to hold a target material and includes a radiation shield that extends between the magnet yoke and the target location. The radiation shield is sized and shaped to attenuate gamma rays emitted from the target material toward the magnet yoke. The isotope production system also includes a beam passage that extends from the acceleration chamber to the target location. The beam passage is at least partially formed by the magnet yoke and the radiation shield of the target system.

Abstract: As typically embodied, the inventive method features bombardment of atomic nuclei with 3He ions in order to effect transmutation of atoms from a first atomic element to a second atomic element. Two notable inventive genres describe transmutation of: oxygen to nitrogen in an oxygen-containing target (e.g., including ZnO film); and, carbon to boron in a carbon-containing target (e.g., including SiC film). According to the former, transmutation of 16O to 15N occurs; more specifically, transmutation of 16O to 15O occurs via nuclear bombardment, and then transmutation of 15O to 15N occurs via decay by positron emission. According to the latter, transmutation of 12C to 11B occurs; more specifically, transmutation of 12C to 11C occurs via nuclear bombardment, and then transmutation of 11C to 11B occurs via decay by positron emission.

Abstract: An apparatus for destroying bacteria is provided which includes a neutron generator and a target polymer film which will receive the impact of neutron emissions. Neutrons impacting the target film produce a second emission of high energy protons which are made to move through an electromagnetic field external to the neutron tube thereby accelerating and steering a generated proton spray. This embodiment is well-suited for treating physical locations known to be infected by pathogenic microorganisms.

Abstract: The invention relates to nuclear technology, and to irradiation targets and their preparation. One embodiment of the present invention includes a method for preparation of a target containing intermetallic composition of antimony Ti—Sb, Al—Sb, Cu—Sb, or Ni—Sb in order to produce radionuclides (e.g., tin—117 m) with a beam of accelerated particles. The intermetallic compounds of antimony can be welded by means of diffusion welding to a copper backing cooled during irradiation on the beam of accelerated particles. Another target can be encapsulated into a shell made of metallic niobium, stainless steel, nickel or titanium cooled outside by water during irradiation. Titanium shell can be plated outside by nickel to avoid interaction with the cooling water.

Abstract: A method is provided for producing first and second radioactive isotopes using an accelerated particle beam that is directed to a first material and the first radioactive isotope is produced by a first nuclear reaction based on the interaction of the particle beam with the first material, said particle beam is also slowed down and subsequently directed to a second material, and the second radioactive isotope is produced by a second nuclear reaction based on the interaction of the particle beam with the second material. The effective cross-section for the induction of the first nuclear reaction at a first peak for a first particle energy is higher than an effective cross-section for the induction of the second nuclear reaction at a second peak for a second particle energy. A corresponding device includes an acceleration unit, a first exposure target having the first material and a second exposure target having the second material.

Abstract: A target apparatus for a radioisotope production system. The target apparatus includes a production chamber that is configured to contain a starting liquid. The production chamber is configured to receive a particle beam that is incident upon the starting liquid thereby generating radioisotopes and transforming a portion of the starting liquid into vapor. The target apparatus also includes a condensing chamber and a fluid channel that fluidly couples the production and condensing chambers and is configured to allow the vapor to flow from the production chamber to the condensing chamber. The condensing chamber is configured to transform the vapor into a condensed liquid.

Abstract: Methods for producing a radioisotope by a charged particle irradiation of a fluid target matrix are provided. A method of producing a radioisotope includes irradiating a fluid target matrix comprising a compound of a target isotope with a charged particle beam to transform at least a portion of the target isotope to the radioisotope, and isolating the radioisotope from the irradiated fluid target matrix. The target isotope may be an isotope of cadmium, an isotope of thallium, an isotope of zinc, an isotope of gallium, an isotope of tellurium, an isotope of molybdenum, an isotope of rhodium, an isotope of selenium, an isotope of nickel, an isotope of yttrium, an isotope of strontium, an isotope of bismuth, an isotope of tungsten, and an isotope of titanium, provided that the target isotope is not Mo-100.

Abstract: Using the device and method of the present invention, high energy photons, or gamma radiation, impinge upon a target comprising a nanomaterial that includes a target isotope, resulting in the release of one or more neutrons from the target isotope. This neutron release creates an effect known as “kinematic recoil,” which results in a recoiling photo-produced radioisotope which is ejected from the nanomaterial and can be harvested in high specific activity.

Abstract: An apparatus and method for fast pulsing of a neutron generator is described in which a series of electrodes are used to first extract deuterium or tritium ions from a plasma contained within an ion source, and then either accelerate or stop the flow of ions to the source, depending upon the voltage potential applied to the downstream electrodes. In one embodiment, the extraction/gating system comprises 3 electrodes, a first extraction electrode which is maintained at the same positive potential as the ion sources, a second electrode maintained at a lower potential to extract ions from the source, and a third electrode which depending on the operational mode is maintained either at the same potential as the second electrode (for beam passage) or at a potential higher than that of the first electrode (for beam blockage).

Abstract: Provided is a modified target assembly in which the target fluid is moved within the target assembly in a manner that increases the effective density of the target fluid within the beam path, thereby increasing beam yield utilizing forced convection. The target may also include optional structures, such as nozzles, diverters and deflectors for guiding and/or accelerating the flow of the target fluid. The target assembly directs the target fluid along an inner sleeve in a direction opposite the direction of the beam current to produce a counter current flow and may also direct the flow of the target fluid away from the inner surface of the inner sleeve and toward a central region in the target cavity. This countercurrent flow suppresses natural convection that tends to reduce the density of the target fluid in the beam path and tends to increase the heat transfer from the target.

Abstract: A system for automatic production of radioisotopes includes an irradiation unit connectable to a cyclotron and having an electrolytic cell; a purification unit for purifying the radioisotope formed in the irradiation unit; two conduits for transferring an irradiated and electrodissolved target from the irradiation unit to the purification unit; and a central control unit for controlling both the operating units and the transfer means. The method for producing radioisotopes is such that the target carrier is not dissolved together with the irradiated target.

Abstract: In a shielded chamber for neutron therapy including a therapy room which has a central beam axis along which a high-energy therapy beam is introduced into the Chamber through one end wall thereof and which includes at the opposite end a labyrinth entrance with at least two shielding wall sections displaced longitudinally along the central beam axis and extending into the room from opposite side walls, the wall sections include structures for causing spallation to thereby generate from the high energy neutrons in the high energy neutron beam a plurality of low energy neutrons which are then moderated by the wall sections.

Abstract: An isotope production target may include an outer diameter wall and an inner diameter wall. An isotope source may be located between the inner diameter wall and the outer diameter wall, and the isotope source may comprise fissile material interspersed with one or more voided regions. A central region may be located within the inner diameter wall, and the central region may be configured to house a neutron thermalization volume.

Abstract: The present invention relates to targets, systems and methods for the cyclotron production of 124I from aluminum telluride (Al2Te3) targets. The systems and methods utilize low energy proton cyclotrons to produce 124I by the 124Te(p,n) reaction from enriched Al2Te3 glassy melts. The 124I is recovered in high yield from the glassy melt by adapted methods of common thermal distillation techniques.

Abstract: The invention relates to the field of nuclear technology and radiochemistry, more specifically to the production and isolation of radionuclides for medical purposes. The method for producing actinium-225 and isotopes of radium comprises irradiating a solid block of metallic thorium of a thickness of 2 to 30 mm, which is contained within a hermetically sealed casing made of a material which does not react with thorium, with a flow of accelerated charged particles with high intensity. The irradiated metallic thorium is removed from the casing and is either heated with the addition of lanthanum and the distillation of radium or is dissolved in nitric acid with the recovery of actinium-225 by extraction. A target for implementing this method consists of blocks of metallic thorium of a thickness of 2 to 30 mm, which are contained within a hermetically scaled casing made of different materials which do not react with thorium.

Abstract: An improved biomarker generator and a method suitable for efficiently producing short lived radiopharmaceuticals in quantities on the order of a unit dose. The improved biomarker generator includes a particle accelerator and a radiopharmaceutical micro-synthesis system. The micro-accelerator of the improved biomarker generator is optimized for producing radioisotopes useful in synthesizing radiopharmaceuticals in quantities on the order of one unit dose allowing for significant reductions in size, power requirements, and weight when compared to conventional radiopharmaceutical cyclotrons.

Abstract: One embodiment of the present invention includes a process for production and recovery of no-carrier-added radioactive tin (NCA radiotin). An antimony target can be irradiated with a beam of accelerated particles forming NCA radiotin, followed by separation of the NCA radiotin from the irradiated target. The target is metallic Sb in a hermetically sealed shell. The shell can be graphite, molybdenum, or stainless steel. The irradiated target can be removed from the shell by chemical or mechanical means, and dissolved in an acidic solution. Sb can be removed from the dissolved irradiated target by extraction. NCA radiotin can be separated from the remaining Sb and other impurities using chromatography on silica gel sorbent. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

Abstract: The invention provides for a method for producing isotopes using a beam of particles from an accelerator, whereby the beam is maintained at between about 70 to 2000 MeV; and contacting a thorium-containing target with the particles. The medically important isotope 225Ac is produced via the nuclear reaction (p,2p6n), whereby an energetic proton causes the ejection of 2 protons and 6 neutrons from a 232Th target nucleus. Another medically important isotope 213Bi is then available as a decay product. The production of highly purified 211At is also provided.

Abstract: The invention provides a method using accelerators to produce radio-isotopes in high quantities. The method comprises: supplying a “core” of low-enrichment fissile material arranged in a spherical array of LEU combined with water moderator. The array is surrounded by substrates which serve as multipliers and moderators as well as neutron shielding substrates. A flux of neutrons enters the low-enrichment fissile material and causes fissions therein for a time sufficient to generate desired quantities of isotopes from the fissile material. The radio-isotopes are extracted from said fissile material by chemical processing or other means.

Abstract: A neutron source includes a low atomic number element target that is bombarded by incident energetic particles to provide a neutron flux. The source receives a controlled flow of liquid gallium that cools the target. The energetic particles may be for example protons or deuterons and the target is housed in a moderator/reflector assembly. Advantageously, the liquid gallium provides improved heat transfer, smaller flow rates and reduced stress on the target in comparison to prior art liquid coolants.

Abstract: The invention relates to producing radiostrontium. The aim of the invention is to release radiostrontium from a large mass of liquid metal rubidium, thereby making it possible to increase the efficiency of radiostrontium production and simplify the production process. Sorption is carried out directly on the inner shell of a target at a temperature of 275-350° C., or by extracting radiostrontium from circulating rubidium by sorption on the heated surface of a trap at a temperature of 220-350° C., or by filtering liquid rubidium through a filtering element made of a porous material resistant to liquid rubidium.

Abstract: Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include irradiation targets for producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more irradiation targets useable with example delivery systems that permit delivery into instrumentation tubes. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while producing desired isotopes.

Abstract: A system for remotely-inducing variable-element electro-chemical-nuclear disruption, the system including an energy delivery device that emits a frequency-adjustable electromagnetic non-photonic continuous-wave beam, and a target area located a distance from the energy delivery device with which the continuous-wave electromagnetic beam interacts wherein the energy delivery device accelerates one or more charged particles or ions within the energy delivery device as a charge antenna.

Abstract: A method for producing 229Th includes the steps of providing 226Ra as a target material, and bombarding the target material with alpha particles, helium-3, or neutrons to form 229Th. When neutrons are used, the neutrons preferably include an epithermal neutron flux of at least 1×1013 n s?1·cm?2. 228Ra can also be bombarded with thermal and/or energetic neutrons to result in a neutron capture reaction to form 229Th. Using 230Th as a target material, 229Th can be formed using neutron, gamma ray, proton or deuteron bombardment.