...that the first rickshaw was invented in 1869 by an American Baptist minister, the Rev. E. Jonathan Scobie, to transport his invalid wife around the streets of Yokohama?
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| Number | Title | Issue Date |
| 7277521 | Detecting special nuclear materials in containers using high-energy gamma rays emitted by fission products A method and a system for detecting the presence of special nuclear materials in a container. The system and its method include irradiating the container with an energetic beam, so as to induce a fission in the special nuclear materials, detecting the gamma rays tha... | 10/02/2007 |
| 7230201 | Apparatus and methods for controlling charged particles Among the embodiments of the present invention, are apparatus, systems, and methods for managing energetic charged particles emitted nearly isotropically from a fusion device. One apparatus of the present invention includes a fusion device in a container and an elec... | 06/12/2007 |
| 7127023 | Batch target and method for producing radionuclide An apparatus for producing a radionuclide includes a target chamber including a beam strike region for containing a liquid and a condenser region for containing a vapor. A particle beam source is operatively aligned with the beam strike region, and a lower liquid co... | 10/24/2006 |
| 6804319 | High specific activity platinum-195m A new composition of matter includes 195mPt characterized by a specific activity of at least 30 mCi/mg Pt, generally made by method that includes the steps of: exposing 193Ir to a flux of neutrons sufficient to convert a portion of the 193... | 10/12/2004 |
| 6751280 | Method of preparing high specific activity platinum-195m A method of preparing high-specific-activity 195mPt includes the steps of: exposing 193Ir to a flux of neutrons sufficient to convert a portion of the 193Ir to 195mPt to form an irradiated material; dissolving the irradiat... | 06/15/2004 |
| 6738446 | System and method for radioactive waste destruction A method for transmuting spent fuel from a nuclear reactor includes the step of separating the waste into components including a driver fuel component and a transmutation fuel component. The driver fuel, which includes fissile materials such as Plutonium239 | 05/18/2004 |
| 6577697 | Field analysis of geological samples using delayed neutron activation analysis A system and method for rapidly analyzing elemental abundances in rock or soil samples (14) under field conditions. The system uses a portable neutron source (12) to allow neutron activation analysis of elements having identifiable radioactive decay chara... | 06/10/2003 |
| 6456680 | Method of strontium-89 radioisotope production Inert gaseous fission products, including beryllium, rubidium, and krypton isotopes, resulting from the operation of a uranyl sulfate water solution nuclear reactor are passed through a delaying device to precipitate out strontium-90, then passed to a sec... | 09/24/2002 |
| 6442226 | Accelerator-driven transmutation of spent fuel elements An apparatus and method is described for transmuting higher actinides, plutonium and selected fission products in a liquid-fuel subcritical assembly. Uranium may also be enriched, thereby providing new fuel for use in conventional nuclear power plants. An... | 08/27/2002 |
| 6252921 | Nuclear isomers as neutron and energy sources The present invention includes the use of N-isomers as a source of energy and of neutrons, and the use of K-isomers as a source of energy when associated with a source of neutrons. Although there is strong indirect evidence for the existence of shape isom... | 06/26/2001 |
| 6222896 | Production of 186Re, 188Re and other radionuclides via inorganic Szilard-Chalmers process Methods for the production of radionuclides suitable for use in radiopharmaceuticals for diagnostic and therapeutic applications, and specifically, to the production of 186 Re, 188 Re and other radionuclides such as 195m P... | 04/24/2001 |
| 6192095 | Xenon-133 radioactive stent for preventing restenosis of blood vessels and a process for producing the same Radioactive stents used in angioplasty on sclerotic coronary arteries without the risk of restenosis can be produced by ion injecting 133 Xe into the surfaces of stents as a nuclide that has a shorter half-life and emits a smaller maximum energ... | 02/20/2001 |
| 6066302 | Method of separation of Cesium-131 from Barium A method of producing and purifying Cs-131 comprising the steps of dissolving irradiated Ba comprised of natural or enriched Ba including Ba-130, Ba-131, and Cs-131 from the decay of Ba-131, in an acid, precipitating the Ba, separating the Cs-131 using an... | 05/23/2000 |
| 6056929 | Method and apparatus for production of radioactive iodine Iodine-125 is produced by neutron irradiation of 124 Xe gas to form 125 Xe and permitting decay of 125 Xe to form 125 I. Irradiation of the xenon-124 is effected in a first chamber within an enclosure and decay ... | 05/02/2000 |
| 5910971 | Method and apparatus for the production and extraction of molybdenum-99 The current invention involves a means for the production and extraction of the isotope molybdenum-99 for medical purposes in a waste free, simple, and economical process. Mo-99 is generated in the uranyl sulphate nuclear fuel of a homogeneous solution nu... | 06/08/1999 |
| 5885465 | Method of separating short half-life radionuclides from a mixture of radionuclides The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixtur... | 03/23/1999 |
| 5875220 | Process for production of radiostrontium A process for the production of radiostrontium consists in that a target of metallic rubidium is bombarded by a flow of accelerating charged particles. The target of irradiated rubidium is melted, whereas the extraction of radiostrontium is carried out by... | 02/23/1999 |
| 5862193 | Production of 186 Re, 188 Re and other radionuclides via inorganic szilard-chalmers process Methods for the production of radionuclides suitable for use in radiopharmaceuticals for diagnostic and therapeutic applications, and specifically, to the production of 186 Re, 188 Re and other radionuclides such as 195m P... | 01/19/1999 |
| 5809394 | Methods of separating short half-life radionuclides from a mixture of radionuclides The present invention is a method of obtaining a radionuclide product selected from the group consisting of 223 Ra and 225 Ac, from a radionuclide "cow" of 227 Ac or 229 Th respectively. The method comprises the... | 09/15/1998 |
| 5802439 | Method for the production of 99m Tc compositions from 99 Mo-containing materials An improved method for producing 99m Tc compositions from 99 Mo compounds. 100 Mo metal or 100 MoO3 is irradiated with photons in a particle (electron) accelerator to ultimately produce 99 ... | 09/01/1998 |
| 5802438 | Method for generating a crystalline 99 MoO3 product and the isolation 99m Tc compositions therefrom An improved method for producing 99m Tc compositions. 100 Mo metal is irradiated with photons in a particle (electron) accelerator to produce 99 Mo metal which is dissolved in a solvent. A solvated 99 Mo product... | 09/01/1998 |
| 5784424 | System for studying a sample of material using a heavy ion induced mass spectrometer source A heavy ion generator is used with a plasma desorption mass spectrometer to provide an appropriate neutron flux in the direction of a fissionable material in order to desorb and ionize large molecules from the material for mass analysis. The heavy ion gen... | 07/21/1998 |
| 5758254 | Method of recovering radioactive beryllium The invention provides a method for recovering metal beryllium from waste beryllium that has become radioactive in the reaction with neutrons, by converting the radioactive beryllium to halogenated beryllium with a halogen gas such as chlorine, bromine or... | 05/26/1998 |
| 5749042 | Bismuth generator method A method for separating 213 Bi from a solution of radionuclides wherein the solution contains a concentration of the chloride ions and hydrogen ions adjusted to allow the formation of a chloride complex. The solution is then brought into contac... | 05/05/1998 |
| 5633900 | Method and apparatus for production of radioactive iodine Iodine-125 is produced by neutron irradiation of 124 Xe gas to form 125 Xe and permitting decay of 125 Xe to form 125 I. Irradiation of the xenon-124 is effected in a first chamber within an enclosure and decay ... | 05/27/1997 |
| 5596611 | Medical isotope production reactor Medical isotopes are produced using a lower power, low cost nuclear reactor which permits the use of all the fission products produced in the reactor. Medical isotopes such as Molybdenum-99 are produced in a reactor operating at a power of 100 to 500 kilo... | 01/21/1997 |
| 5443702 | Laser isotope separation of erbium and other isotopes Laser isotope separation is accomplished using at least two photoionization pathways of an isotope simultaneously, where each pathway comprises two or more transition steps. This separation method has been applied to the selective photoionization of erbiu... | 08/22/1995 |
| 5419819 | Self-regenerating column chromatography The present invention provides a process for treating both cations and anions by using a self-regenerating, multi-ionic exchange resin column system which requires no separate regeneration steps. The process involves alternating ion-exchange chromatograph... | 05/30/1995 |
| 5409677 | Process for separating a radionuclide from solution A process for separating a radionuclide such as radioactive Cu-64 from a mixture containing the radionuclide and a precursor element from which the radionuclide is formed. A weak acid solution is prepared which contains the mixture of the radionuclide and... | 04/25/1995 |
| 5355394 | Method for producing actinium-225 and bismuth-213 The invention relates to a method for producing actinium-225 and bismuth-213. According to the invention, radium-226 is irradiated in the thermal neutron flux of a nuclear reactor, the thorium fraction of the irradiation product is then chemically isolate... | 10/11/1994 |
| 5350542 | Nuclear fuel with isotopically depleted burnable absorber By using AVLIS or other methods capable of providing a depleted isotopic mixture, troublesome isotopes such as Gd154, Gd156 and Er166 are selectively removed from naturally occurring isotopic mixtures, while avoiding the a... | 09/27/1994 |
| 5299241 | Transuranium element transmuting reactor core In a transuranium elements transmuting reactor core in which a reactor is charged with a plurality of fuel assemblies at a core and an amount of a transuranium element to be added is controlled so as to prevent a fuel element contained in the fuel assembl... | 03/29/1994 |
| 5250231 | Nuclear fuel with isotopically depleted burnable absorber By using AVLIS or other methods capable of providing a depleted isotopic mixture, troublesome isotopes such as Gd154, Gd156 and Er166 are selectively removed from naturally occurring isotopic mixtures, while avoiding the a... | 10/05/1993 |
| 5160696 | Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn... | 11/03/1992 |
| 5145636 | Soluble irradiation targets and methods for the production of radiorhenium Water soluble irradiation targets are disclosed for the production of 186 Re and 188 Re. The irradiation targets are selected for both water solubility and absence of elements which would produce contaminating isotopes for medical th... | 09/08/1992 |
| 5053186 | Soluble irradiation targets and methods for the production of radiorhenium Water soluble irradiation targets are disclosed for the production of 186 Re and 188 Re. The irradiation targets are selected for both water solubility and absence of elements which would produce contaminating isotopes for medical th... | 10/01/1991 |
| 4976938 | Hydrogen isotope separation utilizing bulk getters Tritium and deuterium are separated from a gaseous mixture thereof, derived from a nuclear fusion reactor or some other source, by providing a casing with a bulk getter therein for absorbing the gaseous mixture to produce an initial loading of the getter,... | 12/11/1990 |
| 4859431 | Rhenium generator system and its preparation and use A process for preparing a tungsten-188/rhenium-188 generator having a tungstate matrix containing W-188 produced by irradiating tungsten-186 in the tungstate compound. High activity, carrier-free rhenium-188 may be obtained by elution. Substrates for furt... | 08/22/1989 |
| 4729903 | Process for depositing I-125 onto a substrate used to manufacture I-125 sources The invention relates to a process for depositing I-125 on a substrate which comprises contacting a predetermined surface area of substrate with Xe-125 gas, whereby the Xe-125 decays to I-125 and the I-125 in turn deposits as a solid on the surface of the... | 03/08/1988 |
| 4721596 | Method for net decrease of hazardous radioactive nuclear waste materials A method for decreasing the amount of hazardous radioactive reactor waste materials by separation from the waste of materials having long-term risk potential and exposing these materials to a thermal neutron flux. The utilization of thermal neutrons enhan... | 01/26/1988 |