| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 41 | 타겟트리 결합 분리 | KR1020177020401 | 2015-12-24 | KR1020170101947A | 2017-09-06 | 제르윈스키켄; 월터조슈아씨 |
| 타겟트리결합분리(targetry coupled separation)는미리정해진방사선조사생성물의회수를최적화하기위하여타겟(타겟재료및 재료의물리적구조의선택을포함함)과분리화학(separation chemistry)을통해미리정해진방사선생성물의생산을향상시키는것을나타낸다. 본개시내용은, 타겟으로부터하나이상의원하는방사선동위원소를 (방사선조사를통해) 생성하는시스템및 방법을설명하며, 타겟에대한손상없이동일한타겟이다수의방사선조사및 분리동작을겪는것을허용하는시스템및 방법을더 설명한다. 임의의방사선조사생성물의회수전에타겟의완전한용해또는파괴를필요로하는종래기술과대조적으로, 타겟트리결합분리에의해가능하게된 동일한물리적타겟의반복된재사용은종래기술에비하여효율에서의상당한증가와비용에서의감소를나타낸다. | ||||||
| 42 | 동위원소 생성 타겟 | KR1020137004262 | 2011-07-27 | KR101633328B1 | 2016-06-24 | 리즈스티븐리차드; 파머토드스티븐; 켈러스티븐토드; 뭉크마딕켄 |
| 동위원소생성타겟은외경벽 및내경벽을포함할수 있다. 동위원소공급원은내경벽과외경벽의사이에위치할수 있고, 또한, 동위원소공급원은하나이상의비워진영역사이에산재되어있는핵분열성물질을포함할수 있다. 중심영역이내경벽 안에위치할수 있고, 또한, 중심영역은열중성자화체적을수용하도록형성될수 있다. | ||||||
| 43 | 동위원소 생성 타겟 | KR1020157031072 | 2011-07-27 | KR1020150127295A | 2015-11-16 | 리즈스티븐리차드; 파머토드스티븐; 켈러스티븐토드; 뭉크마딕켄 |
| 동위원소생성타겟은외경벽 및내경벽을포함할수 있다. 동위원소공급원은내경벽과외경벽의사이에위치할수 있고, 또한, 동위원소공급원은하나이상의비워진영역사이에산재되어있는핵분열성물질을포함할수 있다. 중심영역이내경벽 안에위치할수 있고, 또한, 중심영역은열중성자화체적을수용하도록형성될수 있다. | ||||||
| 44 | 하이퍼서멀 빔을 제조하는 방법 및 장치 | KR1020100066601 | 2010-07-09 | KR1020110005662A | 2011-01-18 | 우,마크이-션 |
| PURPOSE: A method and an apparatus for manufacturing hyper-thermal beam are provided to prevent temperature and pressure from exceeding out of operational ranges by braking power applied to the apparatus. CONSTITUTION: A hyper-thermal beam system includes a first vacuum system(1040), a source chamber(100), a pipe(107), a diagnosing chamber(2000), a second vacuum system(3050), a controller(5000), and a unistrut(4000). The first vacuum system includes a mechanical pump, a booster pump, a main diffusion pump, and a first transferring stand. The source chamber includes a window and a flange. The diagnosing chamber is capable of including a window. | ||||||
| 45 | Ｉ-125 생산을 위한 내부 순환식 중성자 조사 용기 및 이를 이용한 Ｉ-125 생산방법 | KR1020040109720 | 2004-12-21 | KR1020060070896A | 2006-06-26 | 김헌일; 전병진; 박울재; 한현수 |
| 본 발명은 Xe 가스를 원자로 내의 조사공에서 조사시켜 의료용 방사성동위원소인 125 I를 생산할 수 있도록 한 내부 순환식 중성자 조사용기 및 이 용기를 통한 125 I의 생산방법에 관한 것이다. 본 발명의 중성자 조사용기(1)는 원자로 노심의 조사공(10) 내에 삽입되어 내부에 충진된 Xe 가스를 중성자 조사한 후 붕괴시켜 125 I를 얻도록 되어 있는 중성자 조사용기(1)에 있어서, 상기 조사공(10)에 삽입되어 다량의 중성자에 노출되는 직접 조사부분(3)과 상기 조사공(10)에 삽입되지 않고 노심 상부면 위로 돌출되는 간접 조사부분(5)으로 나누어져 있다. 따라서, 본 발명의 중성자 조사용기 및 이를 이용한 125 I의 생산방법에 의하면, 용기의 하부에서는 Xe 가스에 장시간 중성자가 조사되어 다량의 125 I 가스가 발생되면서도 상단 부분에서는 중성자속을 낮추어 하부에서 발생되어 대류에 의해 상승된 125 I가 126 I 등의 불순핵종으로 전환되는 것을 최소화함으로써 고품위, 고방사능의 125 I를 간단한 장치에 의해 다량으로 생산할 수 있게 된다. I-125, I-126, Xe-124, Xe-125, 중성자, 조사용기, 대류, 내부 순환, 냉각핀, 이중관 | ||||||
| 46 | Base Plate Mounted Core Components for Reliable Rod Assembly and Rapid Field Disassembly | US15789409 | 2017-10-20 | US20190122776A1 | 2019-04-25 | Jeffrey M. McCarty; Jason R. Moore; Nathan J. Payne |
| A mounting assembly that has no threaded connections. A rod with pins or machined features radially extending from a distal end is configured to rotate until the pins align with grooves in a hole through a base plate. The rod is inserted through the hole until the pins are through an opposite surface of the base plate, compressing spring components on the rod. Then the rod is rotated until the pins are aligned with slots that partially extend through the second side of the base plate and the pins become seated in the slots. To remove the rod a tool that engages an articulated feature on the distal end of the rod is installed. The tool rotates the rod until the pins are disengaged from the slots, aligned with the through grooves and passed through the base plate. | ||||||
| 47 | Nuclear Reactor Assemblies, Nuclear Reactor Target Assemblies, and Nuclear Reactor Methods | US15476870 | 2017-03-31 | US20180286528A1 | 2018-10-04 | Jeffrey A. Katalenich; Bruce D. Reid; Robert O. Gates; Andrew W. Prichard; Bruce E. Schmitt; Jim Livingston |
| Reactor target assemblies are provided that can include a housing defining a perimeter of at least one volume and Np or Am spheres within the one volume. Reactor assemblies are provided that can include a reactor vessel and a bundle of target assemblies within the reactor vessel, at least one of the target assemblies comprising a housing defining a volume with Np or Am spheres being within the volume. Irradiation methods are also provided that can include irradiating Np or Am spheres within a nuclear reactor, then removing the irradiated spheres from the reactor and treating the irradiated spheres. | ||||||
| 48 | METHODS AND APPARATUS FOR ADDITIVELY MANUFACTURING STRUCTURES USING IN SITU FORMED ADDITIVE MANUFACTURING MATERIALS | US15909505 | 2018-03-01 | US20180264679A1 | 2018-09-20 | Isabella J. van Rooyen; Clemente J. Parga |
| A method of additively manufacturing a structure comprises nuclear reactor comprises disposing a feed material on a surface of a substrate in a reaction vessel, disposing at least one material formulated and configured to react with the feed material in the reaction vessel, and exposing the feed material and the at least one material to energy from an energy source to react the feed material and the at least one material to form an additive manufacturing material and reaction by-products. The additive manufacturing material is separated from the reaction by-products and exposed to energy from the energy source to form inter-granular bonds between particles of the additive manufacturing material and form a layer of a structure comprising the additive manufacturing material. Related apparatuses and methods are disclosed. | ||||||
| 49 | System and Process for Production and Collection of Radioisotopes | US15341478 | 2016-11-02 | US20180122521A1 | 2018-05-03 | Michael D. Heibel |
| A means for installing material, through a fuel assembly instrument thimble insert, into the existing instrument thimbles in nuclear fuel assemblies for the purpose of allowing the material to be converted to commercially valuable quantities of desired radioisotopes during reactor power operations during a remainder of a fuel cycle and removing the radioisotopes from the core through the reactor flange opening once the fuel assemblies have been removed for refueling. The invention also describes methods that can be used to harvest the irradiated material so it can be packaged for transportation from the reactor to a location where the desired radioisotope(s) can be extracted from the fuel assembly instrument thimble insert. | ||||||
| 50 | METHOD OF PREPARING OF IRRADIATION TARGETS FOR RADIOISOTOPE PRODUCTION AND IRRADIATION TARGET | US15545807 | 2015-01-29 | US20180019032A1 | 2018-01-18 | Beatrice Schuster; Wolfgang Schmid |
| The invention provides a method of preparing irradiation targets for radioisotope production in instrumentation tubes of a nuclear power reactor, the method comprising the steps of: providing a powder consisting of an oxide of a rare earth metal having a purity of greater than 99% and, optionally, an organic binder; pelletizing the powder and optionally the organic binder to form a substantially spherical green body having a diameter of from between 1 to 10 mm; and sintering the spherical green body in solid phase at a temperature of at least 70 percent of a solidus temperature of the rare earth metal oxide powder and for a time sufficient to form a round sintered rare earth metal oxide target having a sintered density of at least 80 percent of the theoretical density. | ||||||
| 51 | Irradiation targets for isotope delivery systems | US12547282 | 2009-08-25 | US09773577B2 | 2017-09-26 | David Allan Rickard; Bradley Bloomquist; Melissa Allen; Nicholas R. Gilman; Jennifer M. Bowie; William Earl Russell, II |
| Example embodiments are directed to methods of producing desired isotopes in commercial nuclear reactors and associated apparatuses 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 irradiation targets for producing radioisotopes in nuclear reactors and instrumentation tubes thereof. Example embodiments include one or more irradiation targets useable with example delivery systems that permit delivery into instrumentation tubes. Example embodiments may be sized, shaped, fabricated, and otherwise configured to successfully move through example delivery systems and conventional instrumentation tubes while producing desired isotopes. | ||||||
| 52 | Target-fueled nuclear reactor for medical isotope production | US12845497 | 2010-07-28 | US09691511B1 | 2017-06-27 | Richard L. Coats; Edward J. Parma |
| A small, low-enriched, passively safe, low-power nuclear reactor comprises a core of target and fuel pins that can be processed to produce the medical isotope 99Mo and other fission product isotopes. The fuel for the reactor and the targets for the 99Mo production are the same. The fuel can be low enriched uranium oxide, enriched to less than 20% 235U. The reactor power level can be 1 to 2 MW. The reactor is passively safe and maintains negative reactivity coefficients. The total radionuclide inventory in the reactor core is minimized since the fuel/target pins are removed and processed after 7 to 21 days. | ||||||
| 53 | SYSTEMS AND METHODS FOR GENERATING ISOTOPES IN NUCLEAR REACTOR STARTUP SOURCE HOLDERS | US14705190 | 2015-05-06 | US20170062085A1 | 2017-03-02 | Thomas A. Caine; Russell E. Stachowski; Dana C. Miranda |
| Irradiation target holders are configured to fit in open locations inside of an operating commercial nuclear core. Holders can be 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 can join 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. | ||||||
| 54 | METHOD AND SYSTEM FOR GENERATING ELECTRICITY USING WASTE NUCLEAR FUEL | US15111829 | 2015-01-22 | US20160372220A1 | 2016-12-22 | Robert F. Bodi; Martin A. Stuart |
| A nuclear reactor adapted for generating energy and/or decontaminating nuclear fuel using a plurality of energy beam generating accelerator devices configured for inducing a photo-fission reaction in the nuclear fuel. | ||||||
| 55 | X-ray targeted bond or compound destruction | US14595431 | 2015-01-13 | US09480856B2 | 2016-11-01 | Michael G. Pravica, Sr. |
| This document provides methods, systems, and devices for inducing a decomposition reaction by directing x-rays towards a location including a particular compound. The x-rays can have an irradiation energy that corresponds to a bond distance of a bond in the particular compound in order to break that bond and induce a decomposition of that particular compound. In some cases, the particular compound is a hazardous substance or part of a hazardous substance. In some cases, the particular compound is delivered to a desired location in an organism and x-rays induce a decomposition reaction that creates a therapeutic substance (e.g., a toxin that kills cancer cells) in the location of the organism. In some cases, the particular compound decomposes to produce a reactant in a reactor apparatus (e.g., fuel cell or semiconductor fabricator). | ||||||
| 56 | Method and system for simultaneous irradiation and elution capsule | US14160667 | 2014-01-22 | US09396825B2 | 2016-07-19 | Bradley Bloomquist; Jennifer Bowie; David Grey Smith; William Earl Russell, II |
| 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. | ||||||
| 57 | Cross-section reducing isotope system | US11946258 | 2007-11-28 | US09362009B2 | 2016-06-07 | 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. | ||||||
| 58 | System And Method For Generating Molybdenum-99 And Metastable Technetium-99, And Other Isotopes | US14949583 | 2015-11-23 | US20160078971A1 | 2016-03-17 | James E. Clayton |
| 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. | ||||||
| 59 | Method of producing isotopes in power nuclear reactors | US12890845 | 2010-09-27 | US09239385B2 | 2016-01-19 | Russell Morgan Fawcett; Randy Peter Gonzales; Russell Patrick Higgins; Robert Bryant James; Michael Thomas Kiernan; William Earl Russell, II; Steven Bruce Shelton; David Grey Smith; Russell Edward 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. | ||||||
| 60 | Systems and methods for efficiently preparing plutonium-238 with high isotopic purity | US13675850 | 2012-11-13 | US09196389B2 | 2015-11-24 | Timothy Creston Bertch; Lloyd Chauncey Brown |
| A method for preparing plutonium-238 (Pu-238) includes using a nuclear reactor in irradiating a liquid containing a neptunium-237 (Np-237) based compound 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 Pu-238 based compound; and separating the Pu-238 based compound from the neptunium based compounds using fractional distillation or a chemical separation method. | ||||||
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