Class / Patent application number | Description | Number of patent applications / Date published |
376158000 | By neutron bombardment | 65 |
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 |
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 |
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 |
20100215137 | Method and apparatus for producing radioisotope - A radioisotope is produced through any of the following reactions using a target material:
| 08-26-2010 |
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 |
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 |
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 |
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 |
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 |
20130129027 | High Flux Neutron Source - 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. | 05-23-2013 |
20130170593 | METHOD OF PRODUCING RADIONUCLIDES - The invention relates to a method of producing radionuclides. According to the method, a target medium comprising at least a target nuclide material is irradiated in an irradiation zone with neutron irradiation. Radionuclides form in the target nuclide material as a result of the irradiation, and at least some of the formed radionuclides are ejected from the target nuclide material. The ejected radionuclides are then captured and collected in a carbon-based recoil capture material which does not have an empty cage structure at crystallographic level. | 07-04-2013 |
20150092900 | AQUEOUS ASSEMBLY AND CONTROL METHOD - 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. | 04-02-2015 |
20150302944 | Combined Moderator/Target For Neutron Activation Process - The present invention relates to combined moderator/target structures that significantly increase the initial energy spectrum of neutrons generated in a nuclear reactor within the thermal range of said spectrum. Said combined moderator/target structures can be applied in all cases, wherein the neutron-capture cross-section of the target—or a certain isotope therein—is at least 2.0 barn for thermal neutrons. | 10-22-2015 |
20160148712 | PRODUCTIONS OF RADIOISOTOPES - The present disclosure generally relates to methods and structures for the production of radioisotopes from the thermal neutron irradiation of selected natural isotopes. The methods, structures and operations are applicable to the production of any radioisotope that may be produced from neutron irradiation. | 05-26-2016 |
20160379728 | YTTRIUM-90 PRODUCTION SYSTEM AND METHOD - A method of producing the therapeutic medical isotope yttrium-90 (Y-90) is provided that includes providing a zirconium target composed at least partially of Zr-90, directing an electron beam onto a high-Z converter to generate a neutron beam having a maximum energy level of 12.1 MeV, and directing the neutron beam onto the zirconium target to isotopically convert at least a portion of the Zr-90 to the Y-90 medical isotope. | 12-29-2016 |
376159000 | Neutron activation analysis | 9 |
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 |
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 |
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 |
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 |
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 |
20130208843 | NEUTRON ACTIVATION ANALYSIS USING A STANDARDIZED SAMPLE CONTAINER FOR DETERMINING THE NEUTRON FLUX - A method for the non-destructive elemental analysis of large-volume samples using neutron radiation and a device for carrying out the method. In the method, the sample is irradiated with fast neutrons in a pulsed manner and the gamma radiation emitted by the sample is measured. The quantity of an element contained in the sample is evaluated after the background signal is subtracted from the area of the photopeak caused by the element in a plot of count rate versus energy. The gamma radiation emitted by a subregion of the sample, the composition of which is known, is evaluated in order to determine the neutron flux at the location of the sample. A metallic enclosure of the sample, such as a standardized waste container, can be selected as such a subregion, for example. A novel evaluation method based on multiparameter analysis can quantify, on the basis thereof, the presence of individual elements more quickly and more accurately than is possible according to the previous prior art. The device is characterized by a sample chamber, which is surrounded by a neutron-reflecting material, in particular graphite. | 08-15-2013 |
20160187270 | System For Active Long Range Detection And Identification Of Special Nuclear Materials Using A High Intensity Particle Beam - A long-range method and a system for reliably detecting and identifying special nuclear materials is provided that relies on the emission of delayed neutrons present in the decay of fission products (delayed neutron precursors) as a unique signature for the special nuclear materials, such as highly enriched uranium ( | 06-30-2016 |
376160000 | Subterranean | 1 |
20150124921 | Downhole Gamma Ray Source Using Neutron Activation - A method is for creating a gamma ray source downhole by creating a radioactive material through irradiation of an inert material by high energy neutrons, wherein the material to be activated may surround the neutron source in close proximity to form a compact gamma ray source. The gamma rays generated by the activation may be used to perform nuclear measurements downhole. | 05-07-2015 |
376170000 | Actinides | 18 |
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 |
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 |
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 | 10 |
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 |
20130003908 | BOILING WATER REACTOR CORE AND FUEL ASSEMBLIES THEREFOR - A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxide containing not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium of. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state. | 01-03-2013 |
20130223578 | 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. | 08-29-2013 |
20140321590 | SMALL, FAST NEUTRON SPECTRUM NUCLEAR POWER PLANT WITH A LONG REFUELING INTERVAL - 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 MW | 10-30-2014 |
20160012922 | Low-contamination, high breeding-yield thorium breeder | 01-14-2016 |
376172000 | Fertile fuel assembly structure or arrangement | 5 |
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 |
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 |
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 |
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 |
376180000 | Formation of uranium isotopes | 1 |
376181000 | Uranium 233 | 1 |
20150139379 | SPECIAL THORIUM-PLUTONIUM HYDRIDES FOR FAST TREATMENT REACTOR - 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. | 05-21-2015 |
376182000 | Formation of plutonium isotopes | 3 |
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 |
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 |
20140133616 | SYSTEMS AND METHODS FOR EFFICIENTLY PREPARING PLUTONIUM-238 WITH HIGH ISOTOPIC PURITY - A method for preparing plutonium-238 (Pu-238) using reactor may include irradiating a liquid containing a neptunium-237 (Np-237) based compounds with neutrons to convert a portion of the Np-237 based compound to a Np-238 based compound; retaining the liquid containing the resulting mixture for a sufficient amount of time for the Np-238 based compound to at least partially convert to a plutonium-238 (Pu-238) based compound. The method further may include separating the Pu-238 based compound from the neptunium based compounds using distillation or chemical method. | 05-15-2014 |
376185000 | Alkali and alkaline elements | 3 |
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 |
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 |
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 | 9 |
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 |
20130136221 | METHOD OF PRODUCING RADIOACTIVE MOLYBDENUM - To provide a method of producing radioactive molybdenum solution suitable for extracting | 05-30-2013 |
20130336437 | APPARATUS AND METHODS FOR TRANSMUTATION OF ELEMENTS - Examples of apparatus and methods for transmutation of an element are disclosed. An apparatus can include a neutron emitter configured to emit neutrons with a neutron output, a neutron moderator configured to reduce the average energy of the neutron output to produce a moderated neutron output, a target configured to absorb neutrons when exposed to the moderated neutron output, the absorption of the neutrons by the target producing a transmuted element, and an extractor configured to extract the desired element. A method can include producing a neutron output, reducing the average energy of the neutron output with a neutron moderator to produce a moderated neutron output, absorbing neutrons from the moderated neutron output with the target to generate a transmuted element, and eluting a solution through the target to extract a desired element. In some examples, the target includes molybdenum-98, and the desired element includes technetium-99m. | 12-19-2013 |
20140133617 | METHOD AND SYSTEM FOR SIMULTANEOUS IRRADIATION AND ELUTION CAPSULE - A capsule for holding, irradiating, and eluting a material is provided. Methods of fabricating and using the capsule are also provided. The capsule may include a multidiameter tube with a first end region, a second end region, and a middle region. Washers and filters are provided in the end regions and the end regions may be sealed using various methods and materials with the end caps press fit into the end regions. The middle region is designed to store a material to be irradiated by a neutron flux source. The capsule components may be made from materials having a low nuclear cross section so that the capsule may be handled safely after an irradiation step is performed. The capsule is also designed to have a symmetric configuration as an elution and irradiation column so that the same capsule may be used to elute the material within the middle region of the capsule after an irradiation step is performed. | 05-15-2014 |
20140192942 | MOLYBDENUM-CONVERTER BASED ELECTRON LINEAR ACCELERATOR AND METHOD FOR PRODUCING RADIOISOTOPES - 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. | 07-10-2014 |
20140348284 | PRODUCTION OF MOLYBDENUM-99 USING ELECTRON BEAMS - An apparatus for producing | 11-27-2014 |
20160042826 | HIGH EFFICIENCY NEUTRON CAPTURE PRODUCT PRODUCTION - An apparatus for use with a neutron source for producing reaction-product nuclei from reactant nuclei includes a plurality of reactant nuclei and a plurality of moderating nuclei. The reactant nuclei and the moderating nuclei are configured to increase the probability of neutron capture by reactant nuclei to achieve enhanced ratios of neutron capture by reactant nuclei to neutron source neutron production. Moderating nuclei and neutron reflection are used to minimize neutron leakage. Temperature control, including cryogenic temperature control, may be used to enhance the rate or probability of reactant nuclei neutron capture. The reactant nuclei may include molybdenum-98 and reaction-product nuclei may include technetium-99m. | 02-11-2016 |
20170236607 | TECHNIQUES FOR ON-DEMAND PRODUCTION OF MEDICAL ISOTOPES SUCH AS MO-99/TC-99M AND RADIOACTIVE IODINE ISOTOPES INCLUDING I-131 | 08-17-2017 |
376187000 | Lead, polonium, bismuth | 1 |
20150357067 | GENERATING ELECTRICITY ON DEMAND FROM A NEUTRON-ACTIVATED FUEL SAMPLE - A technique that uses a thermoelectric generator for generating electrical power employs a safe, initially dormant, stable, non-radioactive fuel sample which is activated on-demand by a neutron source to initiate and control activation of the fuel sample. The technique allows thermoelectric generators to be fully assembled and stored for extended periods of time before they are deployed for use, and then activated on demand only when the need arises for them to generate power. | 12-10-2015 |
376189000 | With reaction product treatment (e.g., recovery, separation) | 10 |
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 |
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 |
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 |
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 |
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 |
20130301768 | SYSTEM AND METHOD FOR COLLECTING 3HE GAS FROM HEAVY WATER NUCLEAR REACTORS - A method of collecting | 11-14-2013 |
20140029710 | PRODUCTION OF TECHNETIUM FROM A MOLYBDENUM METAL TARGET - Recycling of isotopically enriched molybdenum metal targets that are suitable for the large scale cyclotron production of | 01-30-2014 |
20140153684 | Dry Phase Reactor for Generating Medical Isotopes - An apparatus for generating medical isotopes provides for the irradiation of dry-phase, granular uranium compounds which are then dissolved in a solvent for separation of the medical isotope from the irradiated compound. Once the medical isotope is removed, the dissolved compound may be reconstituted in dry granular form for repeated irradiation. | 06-05-2014 |
20150348663 | METHOD OF PRODUCING ISOTOPES IN POWER NUCLEAR REACTORS - 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. | 12-03-2015 |
20160189816 | Targetry coupled separations - Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art. | 06-30-2016 |