Abstract: A compact neutron generator for power production that includes an electron beam source; a target converter material at which an electron beam from said electron beam source is directed, said target converter material comprising low enriched uranium trihydride; a subcritical fuel assembly; at least one neutron spectrum shaper disposed between said subcritical fuel assembly and said target converter material; and a ceramic hydrogen tight cladding enclosing said target converter material.

Abstract: A lightly hydrided/deuterated metallic plutonium-thorium fuel for use in a fast fission pool-type nuclear reactor cooled with liquid metal coolants, including lithium-7 lead eutectic, lead bismuth eutectic or lead. When so used, plutonium-239 is consumed, and merchantable heat is produced along with fissile uranium-233, which can be denatured with uranium-238 and used in light water reactors as fuel.

Abstract: A lightly hydrided/deuterated metallic plutonium-thorium fuel for use in a fast fission pool-type nuclear reactor cooled with liquid metal coolants, including lithium-7 lead eutectic, lead bismuth eutectic or lead. When so used, plutonium-239 is consumed, and merchantable heat is produced along with fissile uranium-233, which can be denatured with uranium-238 and used in light water reactors as fuel.

Abstract: An actinium-227 production device having a plurality of metallic or ceramic caplets, each enclosing a radium-226 compound in redundantly nested sealed cylinders. The radium-226 compound is compacted into a disk and diluted with heat transporting ceramic materials. A thermal neutron shield including spectrum shaping materials to protect actinium-227 produced from exposure to thermal neutrons is included along with a strong neutron absorber to shape the neutron spectrum such that radium-226 nuclei are exposed to neutrons in the higher epithermal energy groups upon entry into the target with an energy of between 20 eV and 1 KeV.

Abstract: A neutron generator and isotope production apparatus and method of using the same to produce commercially and medically useful neutrons. The gamma,n reaction produces neutrons in beryllium and deuterium and the spectrum of the neutrons generated is shaped to optimize capture of the neutrons in a gamma emitting isotope. The gammas interact with target materials to produce large quantities of neutrons.

Abstract: A neutron generator and isotope production apparatus and method of using the same to produce commercially and medically useful neutrons. The gamma,n reaction produces neutrons in beryllium and deuterium and the spectrum of the neutrons generated is shaped to optimize capture of the neutrons in a gamma emitting isotope. The gammas interact with target materials to produce large quantities of neutrons.

Abstract: A method of chemically extracting radium-228, rare earth metals, thorium, the decay products of thorium, and phosphates from thorium-containing ores. The method involves breaking thorium-containing ore into fragments, wetting the fragments with a concentrated strong acid to make a slurry, heating the slurry, passing the heated solution through a first anion exchange column, retaining metals and radium-228 captured on the resin, allowing the radium-228 ions to decay to actinium-228, purifying the actinium-228 fraction, sending the actinium-228 fraction through a capture column, eluting the captured thorium-228 with acid, removing radium from the solution, retaining the radium-228 fraction for isomer in-growth, retaining decay products from the radium-228, separating the REEs from the process stream; and eluting and retaining the REEs.

Abstract: A neutron generator and method of using the same to produce commercial and medical isotopes. Isotopes are transmuted using fission spectrum neutrons produced in neutron multiplier alloys proximate a target isotope. The produced neutron fission spectrum is tailored or shaped by alloys disposed between the multiplier alloys and the target isotope. The tailoring alloys selectively convert the neutron fission spectrum to a nearly coherent distribution of selected high energy, fast, epithermal, or thermal neutrons. The tailoring alloys are engineered to slow the fission spectrum neutrons to the resonance energies of the selected target isotopes through scattering or hydriding of selected components of high temperature aluminum alloys that optimize neutron capture in engineered target alloys.

Abstract: A method and apparatus for directing high energy electrons to a converter material that emits gamma rays, which, in turn interact directly with parent isotopes to produce unstable, short-lived medical isotopes and product isotopes by the gamma, n reaction, or which interact with high-z materials to produce neutrons that then produce valuable isotopes by neutron capture in parent isotopes.

Abstract: A set of alloy formulations is disclosed to use with thorium based nuclear fuels in a fast spectrum reactor; with thorium based nuclear fuels in existing thermal spectrum power reactors; for medical isotope production in the epithermal, the fast, the fission spectrum and the thermal spectra; and to use as fuel in test and experimental reactors that are non proliferative. The alloys form inert metal matrixes to hold fine particles of dispersed thorium containing fuel. The formulations also are useful for the production of medical and commercial isotopes in the high energy, fast and epithermal neutron spectra.