子分类：
| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 101 | Device for the Endogenous Production of Radioisotopes, Particularly for Pet | US11666104 | 2005-10-21 | US20080137791A1 | 2008-06-12 | Marco Sumini; Agostino Tartari; Domiziano Mostacci |
| Device for the endogenous production of radioisotopes, particularly for PET, characterized by comprising: a vacuum chamber (1), the inner surface of which at least partially treated to resistion implantation and inertised with respect to the nuclear reaction products,—a pair of electrodes (4, 5) placed inside said vacuum chamber (1),—a capacitor bank (2),—means (3,16) to connect said capacitor bank (2) to said electrodes (4,5) to generate between the latter an electrical discharge, thus generating plasma and creating conditions for the unfolding of nuclear reactions that generate radioisotopes,—an overall inductance of the equivalent electric circuit of such device not exceeding 50 Nh—means (10) attached to said vacuum chamber (1) for the creation of a vacuum not higher than 10−6 torr—means (11) attached to said vacuum chamber (1) for the insertion, after creating the vacuum, of at least one reaction gas at a pressure apt to guarantee creation of the plasma during discharge and subsequent obtainment of confinement conditions of such plasma of the order of 1015 keV-s/cm3, and—means attached to said vacuum chamber (1) for the extraction of gas and its storage into a gas-chromatographic cylinder. | ||||||
| 102 | Propulsion motor | US11324544 | 2006-01-03 | US20060198484A1 | 2006-09-07 | Jose Conceicao |
| Propulsion motor—a combination was added to the motor and processes, which comprises: a refrigeration system to first wall (13) constituted of tubes (13A) for conduction of refrigerator fluid, the heat exchanger (13B), the fluid storage container (13C) and inside the suction and injection fluid pump (13D). Many targets (1) were added mainly for fast ignition and many beams (4) which can execute the ignition of this targets inside reactor room (16) or inside exhaust (13, 14, 15), wherein the more simple is the explosion of a boosted micro bomb (1) direct in the center of exhaust (13, 14, 15) initiated by laser or radio frequency (3) through methods of explosive micro lenses of high explosives or super high nanostructured explosives. The hydraulic pressure system (15A, 15B, 15C) was included to maintain the magnets (15) together due to mechanical stress, and new materials to form the sheets and tubes involved. The high flow compression generator (8A, 8B, 8C, 8D, 8E) was added to generate currents and magnetic fields applied to z-pinch system, MTF and similar to explode a target (7) by fission, fusion or boosted to generate the energetic beam (4) of the fast ignition. | ||||||
| 103 | Gas target device | US324024 | 1989-03-16 | US4945251A | 1990-07-31 | Volker Bechtold; Hermann Schweickert |
| A gas target device in which a gaseous target is bombarded with charged particles by means of a charged particle accelerator and radioisotopes are produced in a target chamber receiving the gaseous target a vacuum chamber is disposed in front of the gas target device so as to provide safety volume with gas-tight metal foils disposed at both ends thereof which metal foils however are permeable to the charged particles but provide a gas-tight seal with respect to the target chamber of the gas target device and the vacuum system of the accelerator. The metal foils are held by flanges disposed between the housing which are movable relative to one another to permit removal and replacement of the metal foils associated with the flange plates. | ||||||
| 104 | Preparation and use of a 195M-AU-containing liquid | US140781 | 1980-04-16 | US4414145A | 1983-11-08 | Karel J. Panek |
| A method for preparing a .sup.195m Au-containing liquid is provided. In the method, .sup.195m Hg is adsorbed on an adsorption agent and then the daughter radioisotope .sup.195m Au is eluted from the adsorption agent with an eluant containing a gold-complexing agent. The adsorption agent comprises a mercury ion-binding material having a substantially stronger adsorption affinity for mercury ions than for gold ions.Also disclosed are a radioisotope generator capable of producing a .sup.195m Au-containing liquid and a process for conducting a radiodiagnostic examination on a warm-blooded animal using a .sup.195m Au-containing liquid. | ||||||
| 105 | Method of preparing a solution of gallium 68 from germanium 68 | US143106 | 1980-04-23 | US4333911A | 1982-06-08 | Dominique Comar; Christian Loc'h; Bernard Maziere |
| A method of preparing a solution of gallium 68 from germanium 68, wherein the germanium 68 is fixed on particles of tin dioxide and the gallium 68 produced by radioactive decay of the germanium 68 fixed on said particles is then eluted with a solution of hydrochloric acid. | ||||||
| 106 | Low pressure tritiation of molecules | US024192 | 1979-03-27 | US4242186A | 1980-12-30 | Thomas F. Moran; James C. Powers; Mark O. Lively, III |
| Molecules are tritiated by depositing molecules of a substance to be tritiated on a supporting substrate in a vacuum chamber, and then subjecting the substance to low pressures of tritium gas. In a second embodiment of the invention, a substance is tritiated by placing the same near, but not in the path of, an electron beam which traverses a chamber; admitting tritium gas into the chamber; and subjecting the tritium to the electron beam thereby generating vibrationally excited tritium gas molecules which collide and react with the substance thus incorporating tritium atoms into the substance. | ||||||
| 107 | Technetium-99 generators | US951942 | 1978-10-16 | US4206358A | 1980-06-03 | Ralph W. Matthews; Rex E. Boyd |
| A generator for liquid containing .sup.99m Tc has an adsorbant bed of alumina, zirconia or the like and has associated therewith a quantity of an electron scavenging compound of a rare earth, silver or gold so as to maintain elution efficiency during the working life of the generator. The compound may be a rare earth oxide such as ceric oxide typically present as a coating on alumina particles in an amount of about 0.1% by weight or a compound such as silver chloride present in quantities typically of about 5%. The eluant may be sodium or potassium perchlorate in water. | ||||||
| 108 | Nuclide generator for preparing radio-nuclides | US888756 | 1978-03-21 | US4188539A | 1980-02-12 | Helmut Strecker |
| Nuclide generators for preparing sterile and pyrogen-free radioactive solutions consist of a generator column which is provided with radiation shielding and connected to a container for eluting agent and has a connection to a container for eluate. The generator and the container for eluting agent are located in vessels with centering devices, wherein the generator column with its radiation shielding is located in a fixed position relative to the vessel between two centering devices and connected via a cannula to the container for eluting agent which is held in a recess of one centering device in a fixed position relative to the generator column. The other centering device has also a recess for guiding and holding the eluate container which is connected to the generator column via a cannula. | ||||||
| 109 | Rechargeable 99MO/99MTC generator system | US808332 | 1977-06-20 | US4160910A | 1979-07-10 | Alfred K. Thornton; Frank E. Cerone |
| A rechargeable system is provided for the production of sterile, non-pyrogenic, isotonic solutions of radioisotopes such as sodium pertechnetate, which are useful as diagnostic agents in the medical field. A unique feature of the system is that transfer of the recharging supply of the parent isotope from the shipping shield to the generator contained in the generator shield can be effected with minimal exposure to radiation. | ||||||
| 110 | Process for separating fission product molybdenum from an irradiated target material | US769576 | 1977-02-17 | US4123498A | 1978-10-31 | Herman S. Rosenbaum; Douglas R. Packard; Harry A. Levin |
| A process for the separation and collection of molybdenum-99 from an irradiated uranium-containing target material utilizes thermal chromatographic separation. The irradiated target material containing the molybdenum-99 is heated in an oxidizing atmosphere to form an oxidized target material and gaseous molybdenum-99 trioxide. The gaseous molybdenum-99 trioxide is carried by the oxidizing atmosphere along with other vaporized materials to a cooling zone for progressive condensation and collection of the molybdenum-99 trioxide and the other materials in the form of separate deposits. | ||||||
| 111 | Multiple pH alumina columns for molybdenum-99/technetium-99m generators | US687713 | 1976-05-19 | US4041317A | 1977-08-09 | Nabil A. Morcos; Gerald A. Bruno; Thomas A. Haney |
| Molybdenum-99/technetium-99m generators utilizing a multiple pH alumina support medium are disclosed herein. The elution of these generators result in a minimum of low yield problems. | ||||||
| 112 | Generation of a supply of radionuclide | US3774036D | 1972-02-23 | US3774036A | 1973-11-20 | GERHART J |
| A method and apparatus for generating and maintaining an available supply of a radioactive eluate with at least a minimum level of activity. A relatively short-lived daughter radionuclide is produced by the radioactive decay of a relatively longer-lived radionuclide in a radionuclide generating chamber. The daughter radionuclide is separated from the parent radionuclide by use of an eluting solution. The resultant solution is recycled through the generator chamber to replenish and concentrate the amount of daughter radionuclide contained therein. Because a relatively large amount of eluate is produced and maintained at at least a minimum level of radioactivity, it is possible to easily meet fluctuating demands for the daughter radionuclide.
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| 113 | Isotope enrichment process for lanthanide and actinide elements | US3708392D | 1970-12-22 | US3708392A | 1973-01-02 | CAMPBELL D |
| This invention relates to a method of enriching lanthanide and actinide isotopes which comprises loading at least one target lanthanide or actinide cation onto a finely divided particle of synthetic faujasite, heating said located faujasite at a temperature in the range of 350* to 750* C. to fix said cation, irradiating said previously heated faujasite with a neutron source to induce a (n, gamma ) transmutation reaction, and then selectively eluting a transmutation product having an atomic number greater than the irradiated target cation.
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| 114 | Recovering and recycling uranium used for production of molybdenum-99 | US14038424 | 2013-09-26 | US09842664B2 | 2017-12-12 | Sean Douglas Reilly; Iain May; Roy Copping; Gregory Edward Dale |
| 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. | ||||||
| 115 | TARGET DEVICE, RADIONUCLIDE PRODUCING APPARATUS AND METHOD OF PRODUCING A RADIONUCLIDE | US15437145 | 2017-02-20 | US20170251547A1 | 2017-08-31 | Taku ITO |
| Disclosed is a target device (10) having a plurality of target material plates (20a, 20b) for producing a radionuclide, lined up in an overlapped manner, configured to produce the radionuclide when a particle beam is irradiated on the target material plates (20a, 20b), the target device (10) having a front plate group (GRF) composed of target material plates (20a) positioned to the front side the particle beam comes in, and a rear plate group (GRR) composed of the target material plates (20b) positioned to the rear side, and the average thickness of the target material plates (20a) composing the front plate group (GRF) being smaller than the average thickness of the target material plates (20b) composing the rear plate group (GRR). | ||||||
| 116 | RECOVERY OF URANIUM FROM AN IRRADIATED SOLID TARGET AFTER REMOVAL OF MOLYBDENUM-99 PRODUCED FROM THE IRRADIATED TARGET | US14042115 | 2013-09-30 | US20150085964A1 | 2015-03-26 | Sean Douglas REILLY; Iain MAY; Roy Copping; Gregory Edward DALE |
| 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. The uranium is therefore available for reuse, storage, or disposal. | ||||||
| 117 | RECOVERING AND RECYCLING URANIUM USED FOR PRODUCTION OF MOLYBDENUM-99 | US14038424 | 2013-09-26 | US20150085963A1 | 2015-03-26 | Sean Douglas REILLY; Iain MAY; Roy COPPING; Gregory Edward Dale |
| 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. | ||||||
| 118 | NUCLIDE TRANSMUTATION METHOD AND NUCLIDE TRANSMUTATION DEVICE | US14374483 | 2013-01-29 | US20150030115A1 | 2015-01-29 | Yasuhiro Iwamura; Takehiko Itou; Kenji Muta; Shigenori Tsuruga |
| 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. | ||||||
| 119 | Process | US14131921 | 2012-07-13 | US20140140462A1 | 2014-05-22 | Luis A.M.M. Barbosa |
| 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. | ||||||
| 120 | METHODS OF GENERATING ENERGETIC PARTICLES USING NANOTUBES AND ARTICLES THEREOF | US12258568 | 2008-10-27 | US20090147906A1 | 2009-06-11 | Christopher H. Cooper; James F. Loan; William K. Cooper; Alan G. Cummings |
| There is disclosed a method of generating energetic particles, which comprises contacting nanotubes with a source of hydrogen isotopes, such as D2O, and applying activation energy to the nanotubes. In one embodiment, the hydrogen isotopes comprises protium, deuterium, tritium, and combinations thereof. There is also disclosed a method of transmuting matter that is based on the increased likelihood of nuclei interaction for atoms confined in the limited dimensions of a nanotube structure, which generates energetic particles sufficient to transmute matter and exposing matter to be transmuted to these particles. | ||||||
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