Abstract: An anti-breakdown ion source discharge apparatus includes a discharge chamber, a coil support, an upper insulation fixing block, a discharge component and an ion source chamber. The discharge component includes a radio-frequency coil, a lower conductive connector and an upper conductive connector. The radio-frequency coil is fixed on a coil support base; the coil support base is clamped on an inner wall of the bottom of the ion source base; the coil support is along the circumference of the coil support base; the radio-frequency coil passes through the coil support; the upper conductive connector passes by the radio-frequency coil and the coil support base from the outside of the radio-frequency coil and extends into the bottom of the discharge chamber; and the upper insulation fixing block is sleeved over the upper conductive connector and is fixed on the inner wall of the bottom of the ion source chamber.

Abstract: A muon detector includes: a chamber having a maximum cross-sectional dimension of 30 cm or less; a gas sealed inside the chamber ionized by the passage of atmospheric muons to form ions in the chamber; a cathode in the chamber at a first position; an anode in the chamber displaced from the first position, the anode including a mesh of wires; a micropattern gaseous detector arranged between the cathode and the anode and proximate to the anode and configured to receive the ions formed in the chamber between the anode and the cathode and generate electrons in response to each ion sufficient to generate a current in one or more of the mesh wires of the anode; and readout electronics in electrical communication with the anode to detect signals in response to the current generated in the mesh wires.

Abstract: A fast neutron nuclear reactor contains a nuclear reactor core having an array of device locations. Some device locations in the nuclear reactor core contain fissile and fertile nuclear fuel assembly devices. One or more other device locations in the nuclear reactor core contain Doppler reactivity augmentation devices that amplify the negativity of the Doppler reactivity coefficient within the nuclear reactor core. In some implementations, a Doppler reactivity augmentation device can also reduce the coolant temperature coefficient within the nuclear reactor core. Accordingly, a Doppler reactivity augmentation device contributes to a more stable nuclear reactor core.

Abstract: An apparatus including a heating element and a sublimation vessel disposed adjacent the heating element such that the heating element heats a portion thereof. A collection vessel is removably disposed within the sublimation vessel and is open on an end thereof. A crucible is configured to sealingly position a solid mixture against the collection vessel.

Abstract: A radioisotope production apparatus includes a particle accelerator, a first target portion on which a charged particle beam emitted from the particle accelerator is incident and through which the charged particle beam passes, and a second target portion on which the charged particle beam passing through the first target portion is incident. In the first target portion, a target material is held in a beam passage, and a cooling gas supply unit which blows a cooling gas to the target material is provided. In a second target portion, a target substrate is held on a beam axis and a downstream-side surface of the target substrate with respect to the charged particle beam is cooled by cooling water. A total thickness of target foils of the first target portion on the beam axis is smaller than a thickness of the target substrate of the second target portion on the beam axis.

Abstract: The object of the invention relates to a neutron source, which contains a proton accelerator for producing a proton beam, and a target arranged in the trajectory of the proton beam exiting the proton accelerator for producing a neutron beam, to which the proton beam arrives in long, typically 0.5 ms-3 ms impulses, and contains a moderator-reflector system arranged in the vicinity of the target and serving for producing a moderated neutron beam, which has at least one moderator, and a reflector surrounding the moderator and the target, characterized by that at least one statistical neutron chopper is arranged to protrude into the at least one moderated neutron beam exiting channel that modulates at least one neutron beam intensity according to a random or pseudo-random sample as a function of time with its neutron transmittance ability varying according to such pattern.

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: Embodiments provide a method for surveying a hydrocarbon reservoir utilizing a reservoir model. The method includes the step of establishing an ensemble of models reflecting attributes of the hydrocarbon reservoir based on the reservoir model in its present state. The method includes the step of updating the reservoir model by utilizing a volumetric density image of the hydrocarbon reservoir. The volumetric density image can be constructed via muon tomography.

Abstract: Irradiation targets, useful in preparing radioisotopes by exposure of the target to a neutron flux in instrumentation tubes of a nuclear power reactor, are prepared by a method comprising the steps of: providing a powder of an oxide of a rare earth metal having a purity of greater than 99%; consolidating the powder in a mold to form a round green body having a green density of at least 50 percent of the theoretical density; and sintering the spherical green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder to form a round sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density.

Abstract: An apparatus for producing 99Mo from a plurality of 100Mo targets through a photo-nuclear reaction on the 100Mo targets. The apparatus comprises: (i) an electron linear accelerator component; (ii) a converter component capable of receiving the electron beam and producing therefrom a shower of bremsstrahlung photons; (iii) a target irradiation component for receiving the shower of bremsstrahlung photons for irradiation of a target holder mounted and positioned therein. The target holder houses a plurality of 100Mo target discs. The apparatus additionally comprises (iv) a target holder transfer and recovery component for receiving, manipulating and conveying the target holder by remote control; (v) a first cooling system sealingly engaged with the converter component for circulation of a coolant fluid therethrough; and (vi) a second cooling system sealingly engaged with the target irradiation component for circulation of a coolant fluid therethrough.

Abstract: A high-power pulse generator (1), belonging to the LTD family, includes two series of power modules, one series of standard modules (3s) and one series of modified modules (3m), each including a switch (6s; 6m), provided with a trigger electrode (9s; 9m), positioned in series between two capacitors (4s; 4m), the modified modules being designed to produce a pulse at a frequency substantially three times the frequency of the standard modules, and a trigger device (13) designed to control the standard and modified switches (6s; 6m) via a single trigger signal applied to the trigger electrode (9s; 9m) of same. The trigger signal is applied to the switches through a trigger impedance (10m; 10s) that is different between the standard and modified modules, and the plateau slope of the generated pulse depends on the difference between the value of the standard impedance and that of the modified impedance.

Abstract: A defect inspection method according to an embodiment has: exposing a target object to a tracer having higher absorptance for a neutron ray than the target object; radiating the neutron ray to the target object exposed to the tracer; generating at least one neutron image based on the neutron ray having penetrated the target object exposed to the tracer; and detecting a defect of the target object based on the generated at least one neutron image.

Abstract: A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.

Abstract: Illustrative embodiments provide modular nuclear fission deflagration wave reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, modular nuclear fission deflagration wave reactors, modular nuclear fission deflagration wave reactor modules, methods of operating a modular nuclear fission deflagration wave reactor, and the like.

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: Disclosed is a target for isotope production, that comprises a porous, nanostructured material with structure elements having in at least one dimension an average size of 700 run or less, preferably 500 nm or less and most preferably 150 nm or less, said nanostructured material comprising one Of Al2O3, Y2O3 and ZrO2.

Abstract: The invention disclosed herein discloses selected ribose isomers that are useful as PET probes (e.g. [18F]-2-fluoro-2-deoxy-arabinose). These PET probes are useful, for example, in methods designed to monitor physiological processes including ribose metabolism and/or to selectively observe certain tissue/organs in vivo. The invention disclosed herein further provides methods for making and using such probes.

Abstract: An aqueous assembly has a negative coefficient of reactivity with a magnitude. The aqueous assembly includes a vessel and an aqueous solution, with a fissile solute, supported in the vessel. A reactivity stabilizer is disposed within the aqueous solution to reduce the magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly.

Abstract: A process for minimizing waste and maximizing utilization of uranium involves recovering uranium from an irradiated solid target after separating the medical isotope product, molybdenum-99, produced from the irradiated target. The process includes irradiating a solid target comprising uranium to produce fission products comprising molybdenum-99, and thereafter dissolving the target and conditioning the solution to prepare an aqueous nitric acid solution containing irradiated uranium. The acidic solution is then contacted with a solid sorbent whereby molybdenum-99 remains adsorbed to the sorbent for subsequent recovery. The uranium passes through the sorbent. The concentrations of acid and uranium are then adjusted to concentrations suitable for crystallization of uranyl nitrate hydrates. After inducing the crystallization, the uranyl nitrate hydrates are separated from a supernatant. The process results in the purification of uranyl nitrate hydrates from fission products and other contaminants.

Abstract: A processes for recycling uranium that has been used for the production of molybdenum-99 involves irradiating a solution of uranium suitable for forming fission products including molybdenum-99, conditioning the irradiated solution to one suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina. Another process involves irradiation of a solid target comprising uranium, forming an acidic solution from the irradiated target suitable for inducing the formation of crystals of uranyl nitrate hydrates, then forming the crystals and a supernatant and then separating the crystals from the supernatant, thus using the crystals as a source of uranium for recycle. Molybdenum-99 is recovered from the supernatant using an adsorbent such as alumina.

Abstract: A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.

Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

Abstract: In a method of producing isotopes in a light water power reactor, one or more targets within the reactor may be irradiated under a neutron flux to produce one or more isotopes. The targets may be assembled into one or more fuel bundles that are to be loaded in a core of the reactor at a given outage. Power operations in the reactor irradiate the fuel bundles so as to generate desired isotopes, such as one or more radioisotopes at a desired specific activity or stable isotopes at a desired concentration.

Abstract: A nuclide transmutation device and method which enable nuclide transmutation to be performed in a small-scale device compared with large-scale devices are disclosed. The device comprises a structure, and high and low deuterium concentration units are disposed on either side of the structure so as to sandwich the structure therebetween, wherein an electrolytic solution containing heavy water is supplied to the high deuterium concentration unit and is electrolyzed to generate deuterium, thereby producing a state of high deuterium concentration near the high deuterium concentration unit side surface and placing the low deuterium concentration unit in a state of low deuterium concentration relative to the high deuterium concentration unit, causing the deuterium to penetrate through the structure from the high deuterium concentration unit toward the low deuterium concentration unit, and subjecting a substance to nuclide transmutation by reaction with the deuterium.

Abstract: A traveling wave nuclear fission reactor, fuel assembly, and a method of controlling burnup therein. In a traveling wave nuclear fission reactor, a nuclear fission reactor fuel assembly comprises a plurality of nuclear fission fuel rods that are exposed to a deflagration wave burnfront that, in turn, travels through the fuel rods. The excess reactivity is controlled by a plurality of movable neutron absorber structures that are selectively inserted into and withdrawn from the fuel assembly in order to control the excess reactivity and thus the location, speed and shape of the burnfront. Controlling location, speed and shape of the burnfront manages neutron fluence seen by fuel assembly structural materials in order to reduce risk of temperature and irradiation damage to the structural materials.

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 photoneutron conversion target for generating photoneutrons by directing an x-ray beam at the photoneutron conversion target includes an elongated body having a first end and a second end. When the photoneutron conversion target is in use, the x-ray beam enters the body and propagates in a direction from the first end to the second end. The body of the photoneutron conversion target is shaped such that propagation of the x-ray beam is substantially proportionate to an intensity distribution of the x-ray beam, so that the greater an intensity of x-rays of the x-ray beam, the greater the propagation distance of the x-rays within the body of the photoneutron conversion target. The photoneutron conversion target according to the invention can make full use of the x-ray beam so as to increase a yield of photoneutrons.

Abstract: Isotope production system including a particle accelerator configured to produce a particle beam. The isotope production system also includes a target apparatus having a window configured to receive a particle beam and also separate production and condensing chambers. The production chamber is configured to contain a starting liquid and located so that the particle beam 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 fluid channel that extends between and fluidly couples the production and condensing chambers. The fluid channel is configured to allow the vapor to flow from the production chamber into the condensing chamber. The condensing chamber is configured to transform the vapor in the condensing chamber into a condensed liquid.

Abstract: A neutron detector system and method for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. Comparison of the observed neutron count distribution with a Poisson distribution is performed to distinguish fissile material from non-fissile material.

Abstract: A rod assembly for a fuel bundle of a nuclear reactor may include an upper end piece, lower end piece and a plurality of rod segments attached between the upper and lower end pieces and to each other so as to form an axial length of the rod assembly. The rod assembly may include an adaptor subassembly provided at given connection points for connecting adjacent rod segments or a given rod segment with one of the upper and lower end pieces. The connection points along the axial length of the rod assembly may be located where the rod assembly contacts a spacer in the fuel bundle. One (or more) of the rod segments may include an irradiation target therein for producing a desired isotope when a fuel bundle containing one (or more) rod assemblies is irradiated in a core of the reactor.

Abstract: A process for extracting Cs-137 from i) an acidic solution obtained by dissolving an irradiated solid target comprising uranium, ii) an acidic solution comprising uranium which has previously been irradiated in a nuclear reactor, or iii) an acidic solution comprising uranium which has been used as reactor fuel in a homogeneous reactor, the acidic solution i), ii) or iii) having been treated to harvest Mo-99, wherein the process comprises contacting the treated acidic solution with an adsorbent comprising ammonium molybdophosphate (AMP). In an embodiment, the AMP is combined with an organic or inorganic polymeric support, for example AMP synthesised within hollow aluminosilicate microspheres (AMP-C).

Abstract: Methods for acceleration of nuclear transmutation of tritium and radioactive isotopes of metals, and decontamination of metals contaminated with radioactive isotopes by destroying radioactive isotopes to a required level of residual radioactive inventory in metals with simultaneous release of thermal energy via stimulating accelerated transmutation with the half-life parameters describing kinetics of radioactive isotope destruction much shorter than their generally accepted half-life. The stimulus is applied to radioactive metals by placing them into a chamber, exposing them to gaseous substances of the group of hydrogen, deuterium, tritium, or a mixture of these isotopes in a molecular hydrogen form for said gaseous substances to be absorbed by the metals, heating the metals to a temperature of at least 200° C. and maintaining at the said temperature.

Abstract: Nuclear reactor systems and methods are described having many unique features tailored to address the special conditions and needs of emerging markets. The fast neutron spectrum nuclear reactor system may include a reactor having a reactor tank. A reactor core may be located within the reactor tank. The reactor core may include a fuel column of metal or cermet fuel using liquid sodium as a heat transfer medium. A pump may circulate the liquid sodium through a heat exchanger. The system may include a balance of plant with no nuclear safety function. The reactor may be modular, and may produce approximately 100 MWe.

Abstract: The electrochemically active elements of the transition series include both the third, fourth and fifth d block elements, the lanthanides and the actinides. These transition elements have distinct electrochemistry for driving many chemical reactions, in particular the absorption of large volumes of hydrogen and the formation of various hydrides. In particular, Pd, Th, Ti, Ag, Au and La hydrides exhibit anomalous effects. The chemical reactions for forming, decomposing and rearranging the bonds of metal hydrides involve large energies. Furthermore these metal hydrides and mixtures are here demonstrated to exhibit greater strange cold nuclear reactions both cold fission and cold fusion. This invention provides magnetic, x-ray, laser irradiation, pressure, neutron beam, beta ray, alpha ray, gamma ray and catalytic technology for accommodating the special conditions for more controlled and accelerated cold nuclear reactions within the dense plasma (pycno) provided by the lattice of these metal hydrides.

Abstract: A process for producing Tc-99m comprises the steps of contacting a solution of purified Mo-99 with an adsorbent material comprising i) a tin oxide, or ii) a zirconium oxide and a titanium oxide, such that the Tc-99m resulting from the decay of Mo-99 may thereafter be eluted.

Abstract: An apparatus for the generation of thermal energy comprises a reactor vessel containing a volume of pressurized hydrogen; a hydrogen-storing nickel alloy structure in the reactor vessel and configured to have an electric potential applied across it and to be heated to at least about 100 C; and a heat exchange conduit configured to carry a heat exchange medium past the nickel alloy structure so as to allow thermal energy generated in the nickel alloy structure to be transferred to the heat exchange medium. The hydrogen-storing nickel alloy structure comprises a nickel alloy skeletal catalyst mixed with an oxide. The applied electric potential, and the increase in the gas pressure and temperature of the hydrogen from the applied heat, create a reaction between hydrogen nuclei and nickel nuclei in the nickel alloy structure whereby thermal energy is generated by the emission of phonons from the nickel alloy structure.

Abstract: The invention is a renewable energy production process with resonant nano-dust plasma, with the application of a cavity resonator and an acoustic resonator. During the process the acoustic resonator is placed inside the cavity resonator, and create a series of acoustic resonances with a complex plasma made of sub-micron sized carbon dust, hydrogen isotopes and other gases between 10 Pa and 500 kPa at about 2.000° C., thus creating oscillations and thus plasmon polaritons on the surface of carbon dust particles oscillating between 10 kHz-5 GHz and in the terahertz range, which in turn produces heat or electric energy, or creates a series of nuclear transmutations. The invention is an embodiment producing renewable heat, formed by a cavity resonator (30) excited by electromagnetic fields, and an acoustic resonator (10). In the acoustic resonator (10) operated with a number of acoustic resonances, there are nano-sized dust particles (1).

Abstract: The present invention relates generally to both a system and method for determining the composition of an off-gas from a solution nuclear reactor (e.g., an Aqueous Homogeneous Reactor (AHR)) and the composition of the fissioning solution from those measurements. In one embodiment, the present invention utilizes at least one quadrupole mass spectrometer (QMS) in a system and/or method designed to determine at least one or more of: (i) the rate of production of at least one gas and/or gas species from a nuclear reactor; (ii) the effect on pH by one or more nitrogen species; (iii) the rate of production of one or more fission gases; and/or (iv) the effect on pH of at least one gas and/or gas species other than one or more nitrogen species from a nuclear reactor.

Abstract: Exposing isotopes aligned in a sufficiently strong magnetic field to extremely low electromagnetic frequencies results in the production of different isotopes. The method and apparatus also permits the production of subatomic particles.

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: 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: A neutron source rodlet assembly having a separate source capsule assembly that is not encapsulated within the neutron source rodlet assembly. The neutron source rodlet assembly is made up, at least in part, of a neutron source positioning rodlet assembly and the source capsule assembly configured such that assembly together is feasible at a remote site and they can be shipped separately. The source capsule assembly has outer and inner capsules with the outer capsule having a threaded stud at one end that mates with a complimentary threaded recess on the neutron source positioning rodlet assembly. The inner capsule contains a neutron source. The neutron source positioning rodlet assembly and the source capsule assembly are locked together at their interface when the threaded joint is completely tightened. A secondary neutron source material may also be encapsulated within a hollow portion of the neutron source positioning rodlet assembly.

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: Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors 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 assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom.

Abstract: Apparatuses and methods produce radioisotopes in multiple instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from multiple instrumentation tubes during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation tubes during operation of the nuclear plant. Example systems can simultaneously maintain irradiation targets in multiple instrumentation tubes for desired irradiation followed by harvesting.

Abstract: A system and a method for a commercial nuclear repository that turns heat and gamma radiation from spent nuclear fuel into a valuable revenue stream. Gamma radiation from the spent nuclear fuel of the repository may be used to irradiate and sterilize food and other substances. Gamma radiation may also be used to improve the properties of target substances. Additionally, heat decay from the spent nuclear fuel of the repository may be harnessed to heat materials or fluids. The heated fluids may be used, for instance, to produce steam that may make electricity. The heating of working fluids for use in processes, such as heated fluid streams for fermentation or industrial heating, may be transported out of the repository and co-mingled with other heat input, or other fluids.

Abstract: A system for converting a first substance into a second substance, the system including a mixing reactor configured to provide a reactant mixture comprising a first reactant, a second reactant, and a solvent; and a high shear device fluidly connected to the mixing reactor, wherein the high shear device comprises at least one rotor/stator set comprising a rotor and a complementarily-shaped stator symmetrically positioned about an axis of rotation and separated by a shear gap, wherein the shear gap is in the range of from about 10 microns to about 250 microns; and a motor configured for rotating the rotor about the axis of rotation, whereby energy can be transferred from the rotor to the reactants thereby inducing reactions between the first reactant and the second reactant to form a product.

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 assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom.

Abstract: A process is disclosed for generating neutrons with a high degree of anisotrophy in the direction of emission.

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 within a sealed ceramic capsule 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 in a ceramic sublimation tube to afford a copper residue containing Cu67. The Cu67 can be further purified by chemical means.