| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 141 | A METHOD FOR THE MANUFACTURE OF POWDER-FILLED SHAPED BODIES, SHAPED BODIES FOR INTRODUCTION INTO A COMMERCIAL NUCLEAR POWER REACTOR AND THE USE THEREOF | US15525115 | 2015-11-12 | US20180277268A1 | 2018-09-27 | Franz Strohmer; Oliver Arndt; Leila Jaafar |
| To manufacture shaped bodies (10) filled with powder (22) for introduction into the reactor core of a commercial nuclear power reactor a plate made of a metal and/or metalloid is provided with one or more blind holes (14), the blind holes (14) are filled with powder (22), the blind holes (14) filled with powder (22) are reversibly sealed and shaped bodies are cut from the plate so that each blind hole (14) filled with powder (22) is surrounded by a shell made of a metal or metalloid. The powder-filled shaped bodies (10) are used in a ball measuring system for commercial nuclear power reactors and/or for the generation of radionuclides in said reactors. | ||||||
| 142 | Generating isotopes in an irradiation target holder installed in a nuclear reactor startup source holder position | US14705190 | 2015-05-06 | US10026515B2 | 2018-07-17 | Thomas A. Caine; Russell E. Stachowski; Dana C. Miranda |
| A nuclear reactor is operated with irradiation target holders fit in open locations inside of an operating commercial nuclear core and placed with ends at vertical bottom and top of the core or any position therebetween to directly expose holders to nuclear fuel reactions. Holders have ends and overall shape that are joined with existing reactor structures, while fitting closely with fuel and moderator and being easily removable from the same. Holders are fabricated of any reactor-compatible material that will retain irradiation targets and daughter products. Holders securely retain irradiation targets and daughter products of any shape or phase throughout reactor operation. Holders can be installed during reactor outages and irradiated during operation without risk of movement or interference with operation. After a desired period of operation and irradiation, holders can be harvested from the core independent of other core structures and fuel. | ||||||
| 143 | IRRADIATION TARGET PROCESSING SYSTEM | US15549234 | 2016-01-18 | US20180025803A1 | 2018-01-25 | Thomas Fabian Richter; Alexander Sykora; Wilfried Kannwischer; Leila Jaafar |
| An irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core comprises, a target retrieving system, target insertion system and transport gas supply system, mounted on a movable support, wherein: the target retrieving system comprises a target exit port coupled to a target storage container and exhaust system; the target insertion system comprises a target filling device, target retention tubing with target supply junction connectable to the instrumentation tube, and a target diverter coupled to the target filling device, target retention tubing and target retrieving system; and the transport gas supply system comprises a first gas supply tubing coupled to the exit port of the target retrieving system, a second gas supply tubing coupled to a junction for supplying gas to the instrumentation tube, and a transport gas supply junction coupled to the first and second gas supply tubing. | ||||||
| 144 | RADIONUCLIDE GENERATION SYSTEM | US15549215 | 2015-02-09 | US20180025802A1 | 2018-01-25 | Thomas Fabian RICHTER; Lothar WISTUBA; Leila JAAFAR; Oliver ARNDT; Uwe STOLL |
| A radionuclide generation system comprises a tube system configured to permit insertion and removal of irradiation targets into an instrumentation finger of a nuclear reactor, and an irradiation target drive system configured to insert the irradiation targets into the instrumentation finger and to remove the irradiation targets from the instrumentation finger. The radionuclide generation system further comprises an instrumentation and control unit which is linked to an online core monitoring system and being configured to calculate an optimum irradiation time for the irradiation targets based on the actual state of the reactor as provided by the online core monitoring system. | ||||||
| 145 | FLEXIBLE IRRADIATION FACILITY | US15605711 | 2017-05-25 | US20170316845A1 | 2017-11-02 | Peter Bode; Antonia Georgieva Denkova; Hurbert Theodoor Wolterbeek; Rene Martin Gommers; Baukje Elisabeth Terpstra |
| An irradiation facility for a nuclear reactor, a method of removing thermal heat from an irradiated object and adjusting an energy distribution/neutron/gamma-ray flux ratio of irradiation, and a product obtainable by the method. | ||||||
| 146 | Nuclear Fusion of Common Hydrogen | US15316167 | 2014-06-04 | US20170301411A1 | 2017-10-19 | Norris Ray Peery; Ahmad Attaie |
| A process of fusing common hydrogen to: (1) form all of the elements in the Periodic Table of Elements; and, (2) produce excess energy. The process involves controllably initiating the process of electron capture with a hydrogen nucleus, which produces virtual neutrons and a new short-lived negatively charged particle (Negatron). | ||||||
| 147 | METHOD OF MANUFACTURING A RADIATION SOURCE | US15532089 | 2015-12-04 | US20170271038A1 | 2017-09-21 | Matthew David Butts; Charles E. Shanks |
| An equatorial anthropic radiation source and a method of making an equatorial anthropic radiation source are described. The radiation source is useful in diagnostic imaging applications in healthcare or other industries (e.g. computerized three-dimensional segmental imaging; Crompton scattering imaging techniques; radiation detector check and calibration, in particular CdZnTe detectors commonly used in medical imaging). | ||||||
| 148 | Modular nuclear fission waste conversion reactor | US13566078 | 2012-08-03 | US09767926B2 | 2017-09-19 | Robert W. Schleicher; Hangbok Choi; Alan M. Baxter |
| A modular, nuclear waste conversion reactor that continuously produces usable energy while converting U-238 and/or other fertile waste materials to fissionable nuclides. The reactor has a highly uniform, self-controlled, core (2) with a decades-long life and does not require reactivity control mechanisms within the boundary of the active core during operation to retain adequate safety. The exemplary embodiment employs high-temperature helium coolant, a dual-segment (22) initial annular critical core, carbide fuel, a fission product gas collection system, ceramic cladding and structural internals to create a modular reactor design that economically produces energy over multiple generations of reactor cores with only minimum addition of fertile material from one generation to the next. | ||||||
| 149 | MODULAR NUCLEAR FISSION WASTE CONVERSION REACTOR | US13566078 | 2012-08-03 | US20170243662A1 | 2017-08-24 | Robert W. SCHLEICHER; Hangbok CHOI; Alan M. BAXTER |
| A modular, nuclear waste conversion reactor that continuously produces usable energy while converting U-238 and/or other fertile waste materials to fissionable nuclides. The reactor has a highly uniform, self-controlled, core (2) with a decades-long life and does not require reactivity control mechanisms within the boundary of the active core during operation to retain adequate safety. The exemplary embodiment employs high-temperature helium coolant, a dual-segment (22) initial annular critical core, carbide fuel, a fission product gas collection system, ceramic cladding and structural internals to create a modular reactor design that economically produces energy over multiple generations of reactor cores with only minimum addition of fertile material from one generation to the next. | ||||||
| 150 | DEVICE AND METHOD FOR THE PRODUCTION OF RADIOISOTOPES | US15470513 | 2017-03-27 | US20170200520A1 | 2017-07-13 | Taylor Ramon WILSON |
| A dense plasma focus (DPF) to produce positron emitters is provided, where a pulsed device has an anode and a cathode arranged in a vacuum chamber, the anode and cathode being subjected to a high voltage. When the vacuum chamber is filled with a reaction gas and a high voltage generated is applied, a plasma sheath is created and a reaction between the electrodes take place to produce plasmoids resulting in an ion beam that interacts with a reactive gas to produce radio-isotopes. | ||||||
| 151 | METHOD FOR PRODUCING BETA EMITTING RADIOPHARMACEUTICALS, AND BETA EMITTING RADIOPHARMACEUTICALS THUS OBTAINED | US15115635 | 2014-12-18 | US20170169908A1 | 2017-06-15 | Alberto ANDRIGHETTO |
| The present invention relates to a method for producing beta emitting radiopharmaceuticals. The method provides to produce, through a primary accelerator, a low energy proton beam, namely with an energy lower than 70 MeV, preferably with an energy ranging from 32 to 45 MeV, more preferably with energy ranging from 38 to 42 MeV; the low energy proton beam is irradiated on a source target so as to generate a neutral atom beam; the neutral atoms are ionized, extracted by acceleration and preferably subjected to a first focusing; the first focused beam is subjected to a mass separation such to generate a isobaric beam of radioisotopes. The isobaric beam therefore is preferably subjected to a second focusing and it is sent for a predetermined time on a deposition target. Then the irradiated deposition target is subjected to chemical treatment so as to obtain pure beta emitting radiopharmaceuticals. | ||||||
| 152 | METAL OXYGEN FUSION REACTOR | US15334239 | 2016-10-25 | US20170117066A1 | 2017-04-27 | Kenneth N. Swartz; Gary Rodriguez; Roger X. Lenard; David G Schrunk |
| An exothermic fusion reactor is described that uses metal-oxygen transmutation. The process comprises a negatively-charged environment; a moderator comprising at least one noble gas; a metal, including isotopes of hydrogen; and a facilitator comprising at least one element selected from the group consisting of oxygen, carbon, nitrogen, fluorine, phosphorus, sulfur, chlorine, selenium, bromine, iodine, or combinations thereof. | ||||||
| 153 | SYSTEM AND METHOD FOR COLLECTING 3HE GAS FROM HEAVY WATER NUCLEAR REACTORS | US15241553 | 2016-08-19 | US20160372226A1 | 2016-12-22 | 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. | ||||||
| 154 | Method of generating specified activities within a target holding device | US12458399 | 2009-07-10 | US09431138B2 | 2016-08-30 | 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. | ||||||
| 155 | Isotope production target | US13192300 | 2011-07-27 | US09396826B2 | 2016-07-19 | 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. | ||||||
| 156 | Systems and methods for harvesting and storing materials produced in a nuclear reactor | US13709725 | 2012-12-10 | US09305673B2 | 2016-04-05 | Mark R. Heinold; Yogeshwar Dayal; Martin W. Brittingham |
| Systems produce desired isotopes through irradiation in nuclear reactor instrumentation tubes and deposit the same in a robust facility for immediate shipping, handling, and/or consumption. Irradiation targets are inserted and removed through inaccessible areas without plant shutdown and placed in the harvesting facility, such as a plurality of sealable and shipping-safe casks and/or canisters. Systems may connect various structures in a sealed manner to avoid release of dangerous or unwanted matter throughout the nuclear plant, and/or systems may also automatically decontaminate materials to be released. Useable casks or canisters can include plural barriers for containment that are temporarily and selectively removable with specially-configured paths inserted therein. Penetrations in the facilities may limit waste or pneumatic gas escape and allow the same to be removed from the systems without over-pressurization or leakage. Methods include processing irradiation targets through such systems and securely delivering them in such harvesting facilities. | ||||||
| 157 | Systems and methods for managing shared-path instrumentation and irradiation targets in a nuclear reactor | US13709524 | 2012-12-10 | US09224507B2 | 2015-12-29 | Mark R. Heinold; John F. Berger; Milton H. Loper; Gary A. Runkle |
| Systems and methods permit discriminate access to nuclear reactors. Systems provide penetration pathways to irradiation target loading and offloading systems, instrumentation systems, and other external systems at desired times, while limiting such access during undesired times. Systems use selection mechanisms that can be strategically positioned for space sharing to connect only desired systems to a reactor. Selection mechanisms include distinct paths, forks, diverters, turntables, and other types of selectors. Management methods with such systems permits use of the nuclear reactor and penetration pathways between different systems and functions, simultaneously and at only distinct desired times. Existing TIP drives and other known instrumentation and plant systems are useable with access management systems and methods, which can be used in any nuclear plant with access restrictions. | ||||||
| 158 | Systems and methods for retaining and removing irradiation targets in a nuclear reactor | US13710090 | 2012-12-10 | US09208909B2 | 2015-12-08 | Gary A. Runkle; Jack T. Matsumoto; Yogeshwar Dayal; Mark R. Heinold |
| A retainer is placed on a conduit to control movement of objects within the conduit in access-restricted areas. Retainers can prevent or allow movement in the conduit in a discriminatory fashion. A fork with variable-spacing between prongs can be a retainer and be extended or collapsed with respect to the conduit to change the size of the conduit. Different objects of different sizes may thus react to the fork differently, some passing and some being blocked. Retainers can be installed in inaccessible areas and allow selective movement in remote portions of conduit where users cannot directly interface, including below nuclear reactors. Position detectors can monitor the movement of objects through the conduit remotely as well, permitting engagement of a desired level of restriction and object movement. Retainers are useable in a variety of nuclear power plants and with irradiation target delivery, harvesting, driving, and other remote handling or robotic systems. | ||||||
| 159 | Methods and apparatus for suppressing tritium permeation during tritium production | US13473450 | 2012-05-16 | US09202601B2 | 2015-12-01 | Timothy Creston Bertch |
| 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. | ||||||
| 160 | Burnable poison materials and apparatuses for nuclear reactors and methods of using the same | US12385747 | 2009-04-17 | US09165691B2 | 2015-10-20 | William Earl Russell, II; Christopher J. Monetta; Lukas Trosman |
| Example embodiments are directed to materials useable as burnable poisons in nuclear reactors, components using the same, and methods of using the same. Example embodiment burnable poison materials produce desired daughter products as they burn out, thereby permitting placement and use for neutronic characteristic improvement and/or neutron flux shielding in locations conventionally barred as uneconomical. Example embodiment burnable poison materials may include natural iridium and enriched iridium-193. Example embodiment components may be fabricated, shaped, and placed to provide desired burnable poison effects in the reactor core in conventional locations and locations not conventionally used due to economic infeasibility. Example methods include use of example embodiment components, including determining locations benefiting from burnable poison effects, fabricating example embodiment components of a desired amount of example embodiment burnable poison materials, placing the example embodiment components, exposing example embodiment components to flux within the operating nuclear reactor, removing and harvesting example embodiment burnable poison components for desired daughter products produced from example embodiment burnable poison materials. | ||||||
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