| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 61 | System and method for generating molybdenum-99 and metastable technetium-99, and other isotopes | US12928227 | 2010-12-07 | US09196388B2 | 2015-11-24 | James E. Clayton |
| An accelerator based systems are disclosed for the generation of isotopes, such as molybdenum-98 (“99Mo”) and metastable technetium-99 (“99mTc”) from molybdenum-98 (“98Mo”). Multilayer targets are disclosed for use in the system and other systems to generate 99mTc and 98Mo, and other isotopes. In one example a multilayer target comprises a first, inner target of 98Mo surrounded, at least in part, by a separate, second outer layer of 98Mo. In another example, a first target layer of molybdenum-100 is surrounded, at least in part, by a second target layer of 98Mo. In another example, a first inner target comprises a Bremsstrahlung target material surrounded, at least in part, by a second target layer of molybdenum-100, surrounded, at least in part, by a third target layer of 98Mo. | ||||||
| 62 | Cable driven isotope delivery system | US12547249 | 2009-08-25 | US09183959B2 | 2015-11-10 | Bradley Bloomquist; Jennifer M. Bowie; Heather Hatton; Nicholas R. Gilman; William Earl Russell, II; David Grey Smith |
| Provided is an isotope delivery system and a method for irradiating a target and delivering the target to an extraction point. The isotope delivery system may include a cable including at least one target for irradiation, a drive system configured for moving the cable, and a first guide configured to guide the cable for insertion and extraction from a nuclear reactor. The method for irradiating a target and delivering a target may include pushing a cable with an attached target through a first guide and into a nuclear reactor using a drive system, irradiating the target in the nuclear reactor, pulling the cable with the attached irradiated target towards the drive system, pushing the cable with the irradiated target towards a loading/unloading area using the drive system, and placing the irradiated target into a transfer cask, wherein the cable is pulled and pushed by the drive system. | ||||||
| 63 | Special thorium-plutonium hydrides for fast treatment reactor | US12704456 | 2010-02-11 | US08917807B1 | 2014-12-23 | Charles S. Holden |
| 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. | ||||||
| 64 | Fuel rods having irradiation target end pieces | US12000828 | 2007-12-18 | US20140307844A1 | 2014-10-16 | William Earl Russell, II; David Grey Smith |
| Example embodiments are directed to a fuel rod having end pieces on either end containing irradiation targets. Example embodiment end pieces may contain materials that may be converted to desired isotopes when exposed to neutron flux encountered at the end piece position. Example embodiment end pieces may be fabricated from the materials or may otherwise house the materials. Example embodiment end pieces may mate with a variety of full-length and/or part-length fuel rods and may function as upper and/or lower end plugs, mating the fuel rods to upper and/or lower tie plates. | ||||||
| 65 | Method of Producing Isotopes In A Nuclear Reactor With An Irradiation Target Retention System | US13942114 | 2013-07-15 | US20130336436A1 | 2013-12-19 | Melissa ALLEN; Nicholas GILMAN; Heather HATTON; William Earl RUSSELL, II |
| Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors using instrumentation tubes conventionally found in nuclear reactor vessels to expose irradiation targets to neutron flux found in the operating nuclear reactor. Example embodiments include assemblies for retention and producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more retention assemblies that contain one or more irradiation targets and are useable with example delivery systems that permit delivery of irradiation targets. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while containing irradiation targets and desired isotopes produced therefrom. | ||||||
| 66 | SYSTEM AND METHOD FOR COLLECTING 3HE GAS FROM HEAVY WATER NUCLEAR REACTORS | US13852216 | 2013-03-28 | US20130301768A1 | 2013-11-14 | Bhaskar Sur; Lakshman Rodrigo; Richard Didsbury |
| A method of collecting 3He from a nuclear reactor may include the steps of a) providing heavy water at least part of which is exposed to a neutron flux of the reactor, b) providing a cover gas in fluid communication with the heavy water, c) operating the nuclear reactor whereby thermal neutron activation of deuterium in the heavy water produces tritium (3H) and at least some of the tritium produces 3He gas by β− decay and at least a portion of the 3He gas escapes from the heavy water and mixes with the cover gas, d) extracting an outlet gas stream, the outlet gas stream comprising a mixture of the cover gas and the 3He gas and e) separating the 3He gas from the outlet gas stream. | ||||||
| 67 | Apparatuses and methods for production of radioisotopes in nuclear reactor instrumentation tubes | US12071455 | 2008-02-21 | US08437443B2 | 2013-05-07 | William Earl Russell, II; Christopher J. Monetta; David Grey Smith; Russell Edward Stachowski |
| 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. | ||||||
| 68 | ISOTOPE PRODUCTION TARGET | US13192300 | 2011-07-27 | US20120027152A1 | 2012-02-02 | Steven Richard REESE; Todd Stephen PALMER; Stephen Todd KELLER; Madicken MUNK |
| An isotope production target may include an outer diameter wall and an inner diameter wall. An isotope source may be located between the inner diameter wall and the outer diameter wall, and the isotope source may comprise fissile material interspersed with one or more voided regions. A central region may be located within the inner diameter wall, and the central region may be configured to house a neutron thermalization volume. | ||||||
| 69 | NUCLEAR FUEL ASSEMBLY AND RELATED METHODS FOR SPENT NUCLEAR FUEL REPROCESSING AND MANAGEMENT | US13153371 | 2011-06-03 | US20110317794A1 | 2011-12-29 | Francesco VENNERI; Lance Lewis SNEAD |
| 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. | ||||||
| 70 | CABLE DRIVEN ISOTOPE DELIVERY SYSTEM | US12547249 | 2009-08-25 | US20110051875A1 | 2011-03-03 | BRADLEY BLOOMQUIST; JENNIFER M. BOWIE; HEATHER HATTON; NICHOLAS R. GILMAN; WILLIAM EARL RUSSELL, II; DAVID GREY SMITH |
| Provided is an isotope delivery system and a method for irradiating a target and delivering the target to an extraction point. The isotope delivery system may include a cable including at least one target for irradiation, a drive system configured for moving the cable, and a first guide configured to guide the cable for insertion and extraction from a nuclear reactor. The method for irradiating a target and delivering a target may include pushing a cable with an attached target through a first guide and into a nuclear reactor using a drive system, irradiating the target in the nuclear reactor, pulling the cable with the attached irradiated target towards the drive system, pushing the cable with the irradiated target towards a loading/unloading area using the drive system, and placing the irradiated target into a transfer cask, wherein the cable is pulled and pushed by the drive system. | ||||||
| 71 | Method of generating specified activities within a target holding device | US12458399 | 2009-07-10 | US20110009686A1 | 2011-01-13 | Melissa Allen; William Earl Russell, II |
| A method for producing uniform activity targets according to an embodiment of the invention may include arranging a plurality of targets in a holding device having an array of compartments, each target being assigned to a compartment based on a known flux of a reactor core so as to facilitate an appropriate exposure of the targets to the flux based on target placement within the array of compartments. The holding device may be positioned within the reactor core to irradiate the targets. The method may be used to produce brachytherapy and/or radiography targets (e.g., seeds, wafers) in a reactor core such that the targets have relatively uniform activity. | ||||||
| 72 | METHOD AND APPARATUS FOR PRODUCING HYPERTHERMAL BEAMS | US12501315 | 2009-07-10 | US20110006227A1 | 2011-01-13 | Mark Yi-Shuen WU |
| An exemplary apparatus and method for producing a hyperthermal beam is provided. An apparatus may comprise a plasma discharge source, an emission system, and a magnetic source. The plasma discharge source may be configured to receive an elemental source, generate plasma based on the elemental source, and generate one or more neutral atoms of the elemental source. The emission system may be configured to emit a hyperthermal beam, comprising the one or more neutral atoms of the elemental source, from the plasma discharge source through an aperture of the plasma discharge source. The magnetic source may be configured to provide a magnetic field and to collimate the hyperthermal beam in a first direction and control a size of the hyperthermal beam. | ||||||
| 73 | Radioisotope production structures, fuel assemblies having the same, and methods of using the same | US12078705 | 2008-04-03 | US20100284503A1 | 2010-11-11 | David Grey Smith; William Earl Russell, II |
| Example embodiments are directed to tie plate attachments having irradiation targets and/or fuel assemblies having example embodiment tie plate attachments with irradiation targets and methods of using the same to generate radioisotopes. Example embodiment tie plate attachments may include a plurality of retention bores that permit irradiation targets to be contained in the retention bores. Irradiation targets may be irradiated in an operating nuclear core including the fuel assemblies, generating radioisotopes that may be harvested from the spent nuclear fuel assembly by removing example embodiment tie plate attachments. | ||||||
| 74 | Irradiation target retention systems, fuel assemblies having the same, and methods of using the same | US12149408 | 2008-05-01 | US20090274260A1 | 2009-11-05 | William Earl Russell, II; David Grey Smith; Michael S. DeFilippis |
| Example embodiments and methods are directed to irradiation target retention devices that may be inserted into conventional nuclear fuel rods and assemblies. Example embodiment devices may hold several irradiation targets for irradiation during operation of a nuclear core containing the assemblies and fuel rods having example embodiment irradiation target retention devices. Irradiation targets may substantially convert to useful radioisotopes upon exposure to neutron flux in the operating nuclear core and be removed and harvested from fuel rods after operation. | ||||||
| 75 | Cross-Section Reducing Isotope System | US11946258 | 2007-11-28 | US20090135983A1 | 2009-05-28 | William Earl Russell, II; Christopher J. Monetta; Russell Patrick Higgins; Vernon W. Mills; David Grey Smith; Carlton Wayne Clark; Michael S. DeFilippis |
| An isotope production target rod for a power generating nuclear reactor is provided. The isotope production target rod can include at least one rod central body including an outer shell that defines an internal cavity and a plurality of irradiation targets within the internal cavity. The irradiation targets can be positioned in a spatial arrangement utilizing a low nuclear cross-section separating medium to maintain the spatial arrangement. | ||||||
| 76 | Method of producing isotopes in power nuclear reactors | US11002680 | 2004-12-03 | US20070133731A1 | 2007-06-14 | Russell Fawcett; Randy Gonzales; Russell Higgins; Robert James; Michael Kiernan; William Russell; Steven Shelton; David Smith; Russell Stachowski; Lukas Trosman |
| 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. | ||||||
| 77 | Incineration process for transuranic chemical elements and nuclear reactor implementing this process | US11195005 | 2005-08-01 | US20060215799A1 | 2006-09-28 | Bruno Bernardin |
| A process incinerate transuranic chemical elements and nuclear reactor implement this process. In order to incinerate transuranic chemical elements, such as long-lived nuclear waste and plutonium, a nuclear reactor is used in which the core operates at a low level of sub-criticality. This level is chosen substantially equal to the difference βs between a desired fraction βt of delayed neutrons in the core and the real fraction β. An external source of spallation neutrons includes a proton accelerator in which one adjusts the power, in real time, on the neutron flux measured in the core. A supplementary fraction of delayed neutrons equal to the difference βs is thus injected into the reactor core. The reactor then behaves and controls itself like a classical critical reactor. | ||||||
| 78 | Internal circulating irradiation capsule for iodine-125 and method of producing iodine-125 using same | US11133131 | 2005-05-18 | US20060126774A1 | 2006-06-15 | Heon Kim; Ul Park; Byung Jun; Hyon Han |
| A present invention provides an internal circulating irradiation capsule available for the production of iodine-125 and a related production method. The irradiation capsule filled with xenon gas has a lower irradiation part, an upper irradiation part, and a neutron control member. The lower irradiation part is inserted into an irradiation hole of a reactor core and irradiated with a large quantity of neutron directly. When neutron is radiated to the xenon gas, iodine-125 is produced from xenon gas. The upper irradiation part protrudes from the irradiation hole, and iodine-125 is transferred to the upper irradiation part by convection and solidified in the upper part. The neutron control member reduces neutron in the upper part to produce iodine-125 of high purity and radioactivity in a large quantity. | ||||||
| 79 | High specific activity platinum-195m | US10718235 | 2003-11-20 | US06804319B1 | 2004-10-12 | Saed Mirzadeh; Miting Du; Arnold L. Beets; Furn F. Knapp, Jr. |
| 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 193Ir to 195mPt to form an irradiated material; dissolving the irradiated material to form an intermediate solution comprising Ir and Pt; and separating the Pt from the Ir by cation exchange chromatography to produce 195mPt. | ||||||
| 80 | Radioisotope generating apparatus | US10076273 | 2002-02-19 | US20020106046A1 | 2002-08-08 | Masatoshi Fujimoto; Shinichiro Aoshima; Makoto Hosoda; Yutaka Tsuchiya |
| A radioisotope generating apparatus according to the present invention comprises a nuclear reaction section an interior of which is retained in a vacuum; a source supply section for supplying a source material R consisting of a nuclide necessary for generation of the radioisotope, to the nuclear reaction section, an optical system for emitting pulse laser light toward the source material R supplied into the nuclear reaction section and thereby brought into a dispersed state, thereby inducing a nuclear reaction in the source material R to generate the radioisotope, a product nucleus collecting section for collecting a molecule PI having a nucleus of the radioisotope generated in the nuclear reaction section, and a radiation shielding system for preventing outside leakage of radiations generated in the nuclear reaction section. This permits the position of a reaction field of the nuclear reaction to be fixed in a specific small region inside the nuclear reaction section, whereby the space necessary for the nuclear reaction section can be largely decreased. | ||||||
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