| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376158000 | By neutron bombardment | 37 |
| 20130070883 | METHOD OF UTILIZING NUCLEAR REACTIONS OF NEUTRONS TO PRODUCE PRIMARILY LANTHANIDES AND/OR PLATINUM METALS - The method according to the invention is accomplished via neutrons ( | 03-21-2013 |
| 20110129049 | VERY LARGE ENHANCEMENTS OF THERMAL NEUTRON FLUXES RESULTING IN A VERY LARGE ENHANCEMENT OF THE PRODUCTION OF MOLYBDENUM-99 - A large enhancement of neutron flux is realized when a primary target of D | 06-02-2011 |
| 20100002824 | Neutron bundles for energy and element production - Neutron bundles are formed as a result of interactions between polarized atomic core neutrons and anti-polar neutrons injected into atomic cores. Neutron bundles are groups of neutrons that can be produced and used in a process for making elements and isotopes, and also used in a process for the production of nuclear binding energy as the ultimate clean fuel for energy with an unlimited supply. Elements and isotopes are formed upon the introduction of protons onto neutron bundles. Nuclear fusion energy is produced when neutron bundles are made to react with each other in equipment designed for this purpose that includes a neutron bundle nuclear chain reactor. | 01-07-2010 |
| 20090022257 | DIRECT PRODUCTION OF THERMAL ANTINEUTRONS AND ANTIPROTONS - A method for obtaining free thermal antineutrons within the cage-like structure of a fullerene molecule comprising irradiating the fullerene molecule with free neutrons causing free neutrons to be trapped within the fullerene molecule wherein the trapped neutron oscillates between the neutron and antineutron states. A method for producing antiprotons comprising irradiating a fullerene molecule with free neutrons and trapping the neutrons within the fullerene molecule such that the neutrons oscillate between neutron and antineutron states and in the antineutron state decay and produce antiprotons. | 01-22-2009 |
| 20110013738 | Neutron Source For Creation of Isotopes - Disclosed herein are embodiments of systems and methods for creating radioisotopes. In one aspect, a Compact Fusion Neutron Source (CFNS) as described herein, can be used to create radioisotopes. The generation of the radioisotopes can utilize (n,2n), (n,p), (n,d), or (n,α) reactions, which can be caused by the high energy neutrons created by fusion. This abstract is intended for use as a scanning tool only and is not intended to be limiting. | 01-20-2011 |
| 20100215137 | Method and apparatus for producing radioisotope - A radioisotope is produced through any of the following reactions using a target material:
| 08-26-2010 |
| 20100067639 | METHOD AND APPARATUS FOR REDUCING THE RADIOACTIVITY OF A PARTICLE - A method and apparatus for reducing the radioactivity of a particle is disclosed. The method comprises the steps of: accelerating one or more first particle(s) comprising one or more neutron(s), proton(s) and electron(s) to a first velocity; colliding the accelerated particles(s) with one or more second particles in a collision zone located within a housing causing the first particle(s) and second particle(s) to form one or more collision mass(es) comprising alpha particles and electrons or/and protons and electrons, and in which substantially all neutrons of the first or second particles are converted into alpha particles or/and protons and electrons as a result of the collision; controlling the position of the collision mass(es) with electric or/and magnetic fields; and exhausting the collision mass from the housing wherein the collision mass comprises substantially only alpha particles or/and protons and electrons. | 03-18-2010 |
| 20120300890 | SEGMENTED REACTION CHAMBER FOR RADIOISOTOPE PRODUCTION - A reactor that is operable to produce an isotope includes a region for containing a controlled nuclear fission reaction, the region segmented into a plurality of independent compartments, each of the compartments for containing a parent material in an aqueous solution that interacts with neutrons to produce the isotope via a fission reaction. Also provided are methods of producing an isotope using the same. | 11-29-2012 |
| 20120121053 | Very Large Enhancements of Thermal Neutron Fluxes Resulting in a Very Large Enhancement of the Production of Molybdenum-99 Including Spherical Vessels - A large enhancement of neutron flux is realized when a primary target of D | 05-17-2012 |
| 376159000 | Neutron activation analysis | 6 |
| 20130034198 | NOBLE GAS DETECTOR FOR FISSILE CONTENT DETERMINATION - A method and a system for fissile content measurement that utilizes a detector configured to detect fast neutrons. An external radiation source may be used to induce fission in a sample to allow the measurement of a fissile material of the sample with a low spontaneous fission probability. Analyzing the sample may be based on the energy spectrum of emitted neutrons. That is, the energy information regarding the energy of the fast neutrons is obtained, and the fast neutrons as having a high likelihood of originating in a nuclear fission process as opposed to originating in an (alpha,n) reaction by utilizing the obtained energy information are classified to analyze the sample. Alternatively, a position of interaction in the detector of neutron emitted by the sample is measured, and this position is retraced back through intervening material(s) between the detector and the sample to determine the spacial geometry of the sample. | 02-07-2013 |
| 20120183111 | PROMPT GAMMA-RAY DETECTION APPARATUS FOR ANALYZING CHEMICAL MATERIALS USING FEMTOSECOND PULSE LASER-INDUCED NEUTRONS - Disclosed herein is a prompt gamma-ray detection apparatus for analyzing chemical materials using femtosecond pulse laser-induced neutrons, which can be effectively used in the nondestructive inspection of various materials, such as metals, coal, cement, radioactive materials and the like as well as explosives and chemical materials, and which can provide better measurement results for the analysis of basic materials, and a method of measuring prompt gamma-rays using the apparatus. The prompt gamma-ray detection apparatus is advantageous because it can non-destructively analyze the elements in a chemical sample using a femtosecond pulse laser-induced neutron generator that solves the problems of an atomic reactor for research or a radioactive isotope as a neutron radiation source. | 07-19-2012 |
| 20110129050 | Method and Device for Identification of Explosives by means of Neutron Bombardment - A method and device for explosives identification bombards a sample with neutrons the energy of which is to the positron activation energy of nitrogen and to the required energy for a neutron proton nuclear reaction of neutrons with | 06-02-2011 |
| 20110293057 | APPARATUS FOR DETECTING NEUTRONS AND METHODS FOR FABRICATING SUCH APPARATUSES - Apparatuses for detecting neutrons, and methods for fabricating such apparatuses, are provided. The neutron detection apparatus includes a cell configured to hold water. Further, the neutron detection apparatus provides a source of one or more high barns isotopes positioned in the cell and configured to absorb neutrons. Neutron absorption by the high barns isotope in the presence of water causes the formation of H | 12-01-2011 |
| 20090225922 | Neutron flux source and use thereof - The patent specification and claims disclose a neutron flux source supplying both monoenergentic neutrons and a spectrum of neutron energies similar to the neutron emission of | 09-10-2009 |
| 20120275556 | METHOD AND APPARATUS FOR NOVEL NEUTRON ACTIVATION GEOMETRIES IN A FLOWING CARRIER STREAM - The present invention provides a nuclear activation apparatus for one or more fluid samples comprising the following modules;
| 11-01-2012 |
| 376170000 | Actinides | 12 |
| 20110286565 | Techniques for On-Demand Production of Medical Radioactive Iodine Isotopes Including I-131 - 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. | 11-24-2011 |
| 20090074128 | NON-INTRUSIVE METHOD TO IDENTIFY PRESENCE OF NUCLEAR MATERIALS USING ENERGETIC PROMPT NEUTRONS FROM PHOTON-INDUCED FISSION - Methods and systems for non-intrusively detecting the existence of fissile materials in a container via the measurement of energetic prompt neutrons are disclosed. The methods and systems use the unique nature of the prompt neutron energy spectrum from photo-fission arising from the emission of neutrons from almost fully accelerated fragments to unambiguously identify fissile material. The angular distribution of the prompt neutrons from photo-fission and the energy distribution correlated to neutron angle relative to the photon beam are used to distinguish odd-even from even-even nuclei undergoing photo-fission. The independence of the neutron yield curve (yield as a function of electron beam energy or photon energy) on neutron energy also is also used to distinguish photo-fission from other processes such as (γ, n). Different beam geometries are used to detect localized samples of fissile material and also fissile materials dispersed as small fragments or thin sheets over broad regions. These signals from photo-fission are unique and allow the detection of any material in the actinide region of the nuclear periodic table. | 03-19-2009 |
| 20090213977 | Apparatuses and methods for production of radioisotopes in nuclear reactor instrumentation tubes - Example embodiments are directed to apparatuses and methods for producing radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable from nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes. | 08-27-2009 |
| 20110317794 | NUCLEAR FUEL ASSEMBLY AND RELATED METHODS FOR SPENT NUCLEAR FUEL REPROCESSING AND MANAGEMENT - Various embodiments of a nuclear fuel assembly and related methods for processing and managing spent nuclear fuel are disclosed. According to one exemplary embodiment, a nuclear fuel may include a plurality of first fuel rods having a plurality of first fuel elements and a plurality of second fuel rods having a plurality of second fuel elements. Each of the first fuel elements may include uranium dioxide fuel, and each of the second fuel elements may include a plurality of tristructural isotropic fuel particles embedded in a silicon carbide matrix. The plurality of first fuel rods and the plurality of second fuel rods are arranged in a fuel assembly. | 12-29-2011 |
| 376171000 | Breeder or converter reactor structures | 6 |
| 20100166133 | USE OF ISOTOPICALLY ENRICHED NITROGEN IN ACTINIDE FUEL IN NUCLEAR REACTORS - The present invention provides a nuclear fuel comprising an actinide nitride such as | 07-01-2010 |
| 376172000 | Fertile fuel assembly structure or arrangement | 5 |
| 20120183112 | MOLTEN SALT NUCLEAR REACTOR - A molten salt breeder reactor that has fuel conduit surrounded by a fertile blanket. The fuel salt conduit has an elongated core section that allows for the generation of electrical power on a scale comparable to commercially available nuclear reactors. The geometry of the fuel conduit is such that sub-critical conditions exist near the input and output of the fuel salt conduit and the fertile blanket surrounds the input and output of the fuel salt conduit, thereby minimizing neutron losses. | 07-19-2012 |
| 20090268860 | Process for accelerating the breeding and conversion of fissile fuel in nuclear reactors - The present invention related to a novel process for accelerating the breeding and conversion of fissile fuel in various types of nuclear reactors. In said process a movable nuclear fuel ball bed filled with a coolant creeps through the reactor core. The said process could provide higher specific power per unit fuel volume inside the reactor core and proceed on-line refueling, thus requires much less initial fissile fuel inventory per unit power output as compared with the traditional breeding or conversion reactors. The said process has full inherent safety characteristics and could follow the external power demand with the inherent negative temperature coefficient of reactivity. The said process, therefore, is a more efficient and economic approach to meeting the enormous demand of fissile fuel for the forthcoming “second nuclear era”. | 10-29-2009 |
| 20110299645 | Breeding Nuclear Fuel Mixture Using Metallic Thorium - Disclosed is a breeding nuclear fuel mixture including metallic thorium useable in a nuclear power plant, prepared by mixing uranium dioxide (UO | 12-08-2011 |
| 20080232533 | High flux sub-critical reactor for nuclear waste transmulation - A process to safely convert about 95% of the nuclear waste into a usable fuel source is disclosed. The process, involving a sub-critical power reactor and a proliferation-resistant fuel cycle, consumes depleted uranium or thorium fuel with fissionable fuel, including reactor or weapons-grade plutonium. The reactor is comprised of coaxial neutron and energy-amplifying regions separated by moderating and thermal neutron absorbing layers. Control of the water or gas-cooled reactor is provided by plutonium-helium loops with a variable volume flow rate and an external source of neutrons that quickly reacts to any fluctuations of the reactor parameters. A second embodiment of the invention is a compact sub-critical propulsion reactor utilizing fission electric cell and thermo-acoustic technology for electrical power generation. | 09-25-2008 |
| 376173000 | Having internal fertile regions | 1 |
| 20090323881 | Reactor geometry and dry confinement for a nuclear reactor enabling the racquetball effect of neutron conservation dry confinement to be supported by the four-factor and six-factor formula - A nuclear-powered plant of a portable type with a confinement section where the reaction takes place in a core having a reactive thorium/uranium-233 composition, and where an external neutron source is used as a modulated neutron multiplier for the reactor core output. The core is housed in a containment structure that radiates thermal energy captured in a multiple-paths heat exchanger. The exchanger heat energy output is put to use in a conventional gas-to-water heat exchanger to produce commercial quality steam. | 12-31-2009 |
| 376182000 | Formation of plutonium isotopes | 2 |
| 20130114775 | ECONOMICAL PRODUCTION OF ISOTOPES USING QUANTIZED TARGET IRRADIATION - A process for producing isotopes by continuously flowing a liquid stream, carrying capsules of target nuclei (NP-237) in solution, through a nuclear reactor (a TRIGA style nuclear reactor). Upon removal from the core of the nuclear reactor and after allowing for the decay of Np-238 to Pu-238, the capsules are emptied and the mixture of elements and isotopes are chemically separated using solvent extraction or ion exchange. Isotopes that are capable of further processing into Pu-238 are recycled to the core for further processing | 05-09-2013 |
| 20120069946 | Compact Radioisotope Generator - Disclosed are a method and apparatus for making a radioisotope and a composition of matter including the radioisotope. The radioisotope is made by exposing a material to neutrons from a portable neutron source. | 03-22-2012 |
| 376185000 | Alkali and alkaline elements | 3 |
| 20100296616 | METHODS OF PRODUCING CESIUM-131 - Methods of producing cesium-131. The method comprises dissolving at least one non-irradiated barium source in water or a nitric acid solution to produce a barium target solution. The barium target solution is irradiated with neutron radiation to produce cesium-131, which is removed from the barium target solution. The cesium-131 is complexed with a calixarene compound to separate the cesium-131 from the barium target solution. A liquid:liquid extraction device or extraction column is used to separate the cesium-131 from the barium target solution. | 11-25-2010 |
| 20100195781 | NEUTRON BEAM RADIATION APPARATUS - A liquid lithium jet nozzle comprising: an inlet through which liquid lithium flows into the nozzle; an inlet flow channel that receives liquid lithium that flows into the nozzle via the inlet and shapes the flowing liquid lithium to flow in a thin film; and a flow region that receives flowing liquid lithium shaped by the flow channel and in which the liquid lithium flows with at least one large surface of the film exposed. | 08-05-2010 |
| 20120294403 | METHODS AND APPARATUS FOR SUPPRESSING TRITIUM PERMEATION DURING TRITIUM PRODUCTION - A tritium production element for use in a conventional power reactor, and methods of use and making, are provided, wherein the element experiences reduced tritium permeation during irradiation by incorporating a silicon carbide barrier that encapsulates one or more burnable absorber pellets. The tritium production element includes a tubular cladding that encloses a plurality of burnable absorber pellets, such that individual pellets or groups of pellets are disposed within a silicon carbide barrier layer. | 11-22-2012 |
| 376186000 | Molybdenum, technetium | 2 |
| 20110305308 | ADVANCED ONCE-THROUGH PROCESSING FOR EXTRACTING MOLYBDENUM-99 FROM DEUTERIUM AND LOW ENRICHED URANIUM SOLUTIONS - A large enhancement of neutron flux is realized when a primary target of D | 12-15-2011 |
| 20120275557 | Production of Radionuclide Molybdenum 99 in a Distributed and In Situ Fashion - A method and apparatus for producing Mo-99 from Mo-100 for the use of the produced Mo-99 in a Tc-99m generator without the use of uranium is presented. Both the method and apparatus employ high energy gamma rays for the transformation of Mo-100 to Mo-99. The high energy gamma rays are produced by exposing a metal target to a moderated neutron output of between 6 MeV and 14 MeV. The resulting Mo-99 spontaneously decays into Tc-99m and can therefore be used in a Tc-99m generator. | 11-01-2012 |
| 376189000 | With reaction product treatment (e.g., recovery, separation) | 5 |
| 20120219100 | IODINE-125 PRODUCTION SYSTEM AND METHOD - Systems and methods using a double-walled portable container with pressurized gaseous Xe-124 are used as a target for thermal neutron irradiation that generates Xe-125. The portable container is transferred, while submerged in the reactor pool, to a mobile radiation shield container, which are then removed from the reactor pool and connected to the production apparatus that provides handling and recovery functions while properly shielded to minimize radiation exposure. A rapid and efficient transfer of induced Xe-125 and remaining Xe-124 is then accomplished into a clean spiral trap container in which the Xe-125 radioactivity is converted to Iodine-125. After the decay period is completed, Xe-124 and remaining Xe-125 are recovered leaving I-125 deposited on the internal surface of the spiral trap. I-125 is then removed with appropriate solvents. | 08-30-2012 |
| 20110013739 | Methods and apparatuses for producing isotopes in nuclear fuel assembly water rods - Example embodiments are directed to methods and apparatuses for generating desired isotopes within water rods of nuclear fuel assemblies. Example methods may include selecting a desired irradiation target based on the target's properties, loading the target into a target rod based on irradiation target and fuel assembly properties, exposing the target rod to neutron flux, and/or harvesting isotopes produced from the irradiation target from the target rod. Example embodiment target rods may house one or more irradiation targets of varying types and phases. Example embodiment securing devices include a ledge collar and/or bushing that support target rods within a water rod and permit moderator/coolant flow through the water rod. Other example embodiment securing devices include one or more washers with one or more apertures drilled therein to hold one or more example embodiment target rods in a water rod while permitting coolant/moderator to flow through the water rod. | 01-20-2011 |
| 20110305309 | METHODS AND APPARATUS FOR SELECTIVE GASEOUS EXTRACTION OF MOLYBDENUM-99 AND OTHER FISSION PRODUCT RADIOISOTOPES - Methods and apparatus are provided for producing and extracting Mo-99 and other radioisotopes from fission products that overcome the drawbacks of previously-known systems, especially the excessive generation of radioactive wastes, by providing gas-phase extraction of fission product radioisotopes from a nuclear fuel target using a mixture including halide and an oxygen-containing species with heat to convert the fission product radioisotopes to gas (e.g., Mo-99 to MoO | 12-15-2011 |
| 20120300891 | METHODS OF SEPARATING MEDICAL ISOTOPES FROM URANIUM SOLUTIONS - Provided are methods to separate an isotope from a first solution including uranium. The methods may include (a) cleaning the first solution to form a second solution including the uranium and a third solution including the isotope; (b) oxidizing the third solution to form an oxidized isotope; and (c) separating the oxidized isotope. | 11-29-2012 |
| 20110280356 | Techniques for On-Demand Production of Medical Isotopes Such as Mo-99/Tc-99m and Radioactive Iodine Isotopes Including I-131 - 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 (m, f) reactions in U- | 11-17-2011 |
