| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 121 | 高同位体純度のプルトニウム−２３８を効率的に調製するためのシステムおよび方法 | JP2015541812 | 2013-10-31 | JP2016503339A | 2016-02-04 | バーチ，ティモシー，クレストン; ブラウン，ロイド，チョウンシー |
| 反応炉を利用してプルトニウム−238(Pu−238)を調製する方法は、中性子をネプツニウム−237(Np−237)系化合物に照射することにより、一部のNp−237系化合物をNp−238系化物に変換させる工程と、得られた混合物を含む液体を、Np−238系化合物が少なくとも部分的にプルトニウム−238(Pu−238)系化合物に変換するのに十分な時間、保持する工程と、を含み得る。当該方法は、蒸留法または化学的方法を用いて、ネプツニウム系化合物からPu−238系化合物を分離する工程をさらに含み得る。 | ||||||
| 122 | 原子炉の炉心内又は炉心の周囲で試料を照射する装置 | JP2015009779 | 2015-01-21 | JP2015145871A | 2015-08-13 | ムーラン ダミアン; クリスティン セバスチャン |
| 【課題】原子炉の炉心内又は炉心の周囲で試料に放射線照射する装置を提供する。 【解決手段】チャンバ7を区切る二重壁格納容器6と、チャンバ7に収容されたレセプタクル4であって、格納容器の内側壁8から離れて保持され、冷却材を収容するように設計されたレセプタクル4と、試料ホルダ2であって、その自由端がレセプタクル内に配置された試料ホルダ2とを有し、レセプタクルの内部が、レセプタクルの外側と流体連通しており、格納容器6の内側壁8とレセプタクル4との間の容積が、冷却材クッションガスと呼ばれるガス又はガス混合物で充満される。 【選択図】図1 |
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| 123 | 核燃料集合体のウォータロッドにおいて同位体を製造する方法及び装置 | JP2010155314 | 2010-07-08 | JP5727727B2 | 2015-06-03 | デビッド・グレイ・スミス; ウィリアム・アール・ラッセル,ザ・セカンド |
| 124 | 同時照射及び溶出カプセルおよびその使用方法 | JP2010091880 | 2010-04-13 | JP5634106B2 | 2014-12-03 | ブラッドリー・ブルームクウィスト; ジェニファー・ボウイ; デヴィッド・グレイ・スミス; ウィリアム・アール・ラッセル，ザ・セカンド |
| 125 | Systems and methods for processing irradiation targets through nuclear reactor | JP2012232461 | 2012-10-22 | JP2013140136A | 2013-07-18 | YOGESHWAR DAYAL; EARL F SAITO; JOHN F BERGER; MARTIN W BRITTINGHAM; STEPHEN K MORALES; JEFFREY M HARE |
| PROBLEM TO BE SOLVED: To provide apparatuses and methods which produce radioisotopes in instrumentation guide tubes inside nuclear reactors in commercial operation.SOLUTION: Irradiation targets may be inserted into and removed from instrumentation guide tubes inside nuclear reactors during operation and converted to radioisotopes otherwise unavailable during operation of commercial nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes or other desired materials at several different origin and termination points accessible outside an access barrier such as a containment building, drywell wall, or other access restriction preventing access to instrumentation guide tubes inside nuclear reactors during operation of the nuclear plant. | ||||||
| 126 | Modular nuclear fission waste conversion reactor | JP2012552113 | 2011-02-04 | JP2013519094A | 2013-05-23 | バクスター、アラン・エム; チョイ、ハンボック; シュライヒャー、ロバート・ダブリュー |
| Ｕ−２３８及び／又は他の親廃棄物材料を核分裂可能な核種に転換しながら、使用可能なエネルギーを連続的に生産するモジュール式核分裂廃棄物転換炉。 原子炉は、数十年の寿命を備え、運転中に十分な安全を維持するための活性炉心の境界内の反応度制御機構を必要としない、非常に均一な、自己制御式の炉心２を有する。 例示的な実施形態は、高温ヘリウム冷却材、二重セグメント２２初期環状臨界炉心、炭化物燃料、核分裂生成物ガス捕集システム、セラミック被覆及び内部構造物を使用し、１つの世代から次の世代へと、親物質材料の最小限の追加のみで、炉心の複数世代にわたって経済的にエネルギーを生成するモジュール式原子炉設計を形成する。 | ||||||
| 127 | Fuel rod assembly for nuclear reactors | JP2011195608 | 2011-09-08 | JP2012058244A | 2012-03-22 | RUSSELL PATRICK HIGGINS; VERNON W MILLS; DAVID GLAY SMITH; GERALD ANTHONY LUCIANO; VAN SLYKE ROGER HOWARD; WILLIAM R RUSSELL II; BLOOMQUIST BRADLEY D |
| PROBLEM TO BE SOLVED: To provide a multi-segment fuel rod that includes a plurality of fuel rod segments.SOLUTION: Fuel rod segments are removably mated to each other via mating structures in an axial direction. An irradiation target is disposed within at least one of the fuel rod segments, and at least a portion of at least one mating structure includes one and/or more combinations of neutron absorbing materials. A plurality of fuel rod segments include a first fuel rod segment removably mated to a second fuel rod segment; the first fuel rod segment may have a male connecting member (330) and the second fuel rod segment may have a female connecting member (350) capable of receiving the male connecting member. | ||||||
| 128 | Irradiation target retention assemblies for isotope delivery systems | JP2010185694 | 2010-08-23 | JP2011047937A | 2011-03-10 | ALLEN MELISSA; GILMAN NICHOLAS R; HATTON HEATHER; RUSSELL WILLIAM EARL II |
| <P>PROBLEM TO BE SOLVED: To provide a target holding system which quickly and readily forms and collects radioisotopes inside a nuclear reactor. <P>SOLUTION: One embodiment relates to a method of manufacturing desired isotope in commercial furnaces and associated devices by using an instrumentation pipe seen conventionally in reactor vessels for exposing the irradiation target to neutron flux generated inside a nuclear reactor in operation. The embodiment includes a structure which holds and manufactures radioisotope in the nuclear reactor and the instrumentation pipe 50. The embodiment includes one or more holding structures which contains one or more irradiation targets and is usable with a delivery system which sends out irradiation targets. The embodiment, wherein while the irradiation targets and desired isotope manufactured from irradiation targets are contained, the size and shape may be prescribed, manufactured and constituted so as to move through the delivery system and the conventional instrumentation pipe 50 without problems. <P>COPYRIGHT: (C)2011,JPO&INPIT | ||||||
| 129 | Method and apparatuses for producing isotopes in nuclear fuel assembly water rods | JP2010155314 | 2010-07-08 | JP2011022143A | 2011-02-03 | DAVID GLAY SMITH; RUSSELL WILLIAM EARL II |
| PROBLEM TO BE SOLVED: To provide a method and an apparatus for generating desired isotopes within water rods of nuclear fuel assemblies. SOLUTION: The method includes selecting (S300) a desired irradiation target (110) based on the chracteristics of the target; loading (S310) the irradiation target into a target rod (100) based on irradiation target (110) and fuel assembly (10) properties; exposing (S330) the target rod (100) to neutron flux; and/or harvesting isotopes generated from the irradiation target (110) from the target rod (100). In one embodiment, the securing device includes a ledge collar (500) and/or bushing (501) that support the target rod (100) within a water rod (22) and permit moderator/coolant to flow through the water rod (22). In another embodiment, the securing device includes one or more washers, with one or more apertures drilled therein to hold the target rod (100) in the water rod (22), while permitting coolant/moderator to flow through the water rod (22). COPYRIGHT: (C)2011,JPO&INPIT | ||||||
| 130 | Brachytherapy and radiography target holding device | JP2010156345 | 2010-07-09 | JP2011015970A | 2011-01-27 | ALLEN MELISSA; RUSSELL WILLIAM EARL II; RICKARD DAVID ALLAN; SHAH JIGAR RAJENDRA |
| PROBLEM TO BE SOLVED: To provide a brachytherapy and radiography target holding device which capture seeds with uniform radioactivity.SOLUTION: A target holding device (100) includes a plurality of target plates (102), each target plate (102) having a first surface and an opposing second surface, wherein the first surface has a plurality of holes (202). A shaft (108) may be used to facilitate the alignment and joinder of the target plates (102) such that the first surface of one target plate (102) contacts a second surface of an adjacent target plate (102). The target holding device (100) may optionally include end plates (106) arranged to sandwich the target plates (102) therebetween and/or separator plates (104) alternately arranged with the target plates (102). | ||||||
| 131 | Method of manufacturing a radioactive molybdenum and equipment | JP2006286159 | 2006-10-20 | JP4618732B2 | 2011-01-26 | 悦男 石塚; 克嘉 蓼沼 |
| 132 | Burnable poison material and apparatus for nuclear reactor, and method of using the same | JP2010093626 | 2010-04-15 | JP2010249820A | 2010-11-04 | RUSSELL WILLIAM EARL II; MONETTA CHRISTOPHER J; TROSMAN LUKAS |
| <P>PROBLEM TO BE SOLVED: To provide materials useable as burnable poison materials in nuclear reactors, components which uses the materials, and to provide a method which uses the materials. <P>SOLUTION: Since burnable poison materials generates a desired daughter nuclide, when burning is finished, arrangement and use of the burnable poison materials for improving neutron characteristics and/or neutron flux shielding at a location where the poison is refrained from being used hitherto, because of its poor economical efficiency, become possible. The burnable poison materials related to embodiment may contain natural iridium and enriched iridium-193. The components may be manufactured, shaped and arranged in order to acquire a desired burnable poison effect, at a location in a core, where the burnable poison is not used hitherto, and at a location, where the burnable poison materials are not used hitherto, because their use is considered as being impossible, due to economic reasons. <P>COPYRIGHT: (C)2011,JPO&INPIT | ||||||
| 133 | Fuel bundle including at least one isotope production rod | JP2008294020 | 2008-11-18 | JP2009133855A | 2009-06-18 | FUNG POON CINDY; MILLS VERNON W; RUSSELL II WILLIAM EARL |
| PROBLEM TO BE SOLVED: To lay out one or more isotope production rods in a fuel bundle. SOLUTION: An illustrative embodiment of the present invention is intended for the layout of one or more isotope production rods (100) in the fuel bundle (10). The layout may be based on any or their combination of numerous factors such as a relative position of a core monitor, a type of a radioisotope being produced, the half-lives, or the duration of decay, of the radioisotope, a neutron absorption factor of a target isotope to produce the radioisotopes, a desired specific activity of the radioisotope being produced, a quantity of neutron flux in various domains of the fuel bundle (10) and a duration when the target isotope/the radioisotope is expected to remain in a fission reactor until it is removed (or harvested). COPYRIGHT: (C)2009,JPO&INPIT | ||||||
| 134 | Nuclear power generation utilizing separation and recovery method and this rare element fp of spent nuclear fuel - fuel cell power generation symbiotic system | JP2001362251 | 2001-11-28 | JP3549865B2 | 2004-08-04 | 雄一 佐野; 正基 小澤; 佳彦 篠田 |
| 135 | Incineration method as well as the reactor that was carrying out the method for transuranic chemical element | JP2001566144 | 2001-03-06 | JP2003529058A | 2003-09-30 | ブリュノ・ベルナルダン |
| (57)【要約】 本発明は、超ウラン的化学元素の焼却方法ならびにそのような方法を実施した原子炉に関するものである。 例えば半減期の長い核廃棄物やプルトニウムといったような超ウラン的化学元素を焼却するために、コア（１２）が準臨界という低レベルで動作している原子炉を使用する。 このレベルは、コア（１２）内における遅延中性子割合の所望値（β t ）と実際値（β）との間の差（β s ）に実質的に等しいように選択される。 破砕中性子の外部供給源は、プロトン加速器（２２）を備え、この加速器のパワーが、コア内において測定された中性子束に基づいてリアルタイムで調節される。 これにより、差（β s ）に等しい分だけの補助的遅延中性子割合が、原子炉コア内に注入される。 この場合、原子炉は、古典的臨界炉と同様に振る舞うとともに同様に制御される。 | ||||||
| 136 | Manufacture of 99mo generating target using low level enriched uranium and 99mo generating target made of low level enriched uranium | JP26160194 | 1994-09-30 | JPH07218697A | 1995-08-18 | TOOMASU SHII UIENSETSUKU; JIEIMUSU II MATOSU; JIERARUDO ERU HOFUMAN |
| PURPOSE: To provide manufacture of a<99> MO generating target using low level enriched uranium and a<99> MO generating target made of low level enriched uranium. CONSTITUTION: A primary target 10 comprises an inner side tube 12, outer side tube 26 and a foil 22 interposing therebetween. The inner side tube 12 comprises an outer side surface, first end portion 14 and second end portion 16. The foil 22 is made of a fissile material and almost covers the outer side surface of the inner side tube 12. The outer side tube 26 comprises an inner side surface, first end portion 14 and second end portion 16. The inner side surface of the outer side tube 26 accommodates the inner side tube 12 almost covered by the foil 22. The inner side tube 12 and outer side tube 26 contacts in a condition of being pressed toward each other and thus good mechanical contacts between the inner side tube and foil 22, and between the outer side tube 26 and foil 22 are secured. | ||||||
| 137 | Production unit of radioactive isotope, especially cobalt 60 | JP14525090 | 1990-06-01 | JPH0329899A | 1991-02-07 | PIEERU KUURON |
| PURPOSE: To produce a radioactive isotope continuously and economically using a simple means by disposing a production unit representatively at a protective assembly around a nuclear core and making a central channel for receiving a capsule containing a sample. CONSTITUTION: The body 1 of the production unit has the outside dimensions and the profile similar to those of one protective assembly interposed between the fuel parent substance bracket and a containment on the outside of a fast neutron reactor and disposed in place thereof. A holder holding a capsule 7 containing a sample comprises a tubular sleeve moderator 9 having a central channel 11 for temporarily receiving the capsule 7 during irradiation. The acting part of the unit is present at the longitudinal parts AB matching the arrangement of the irradiation 9 and a material rod 13 to be irradiated is encapsulated in the removable capsule 7. Upon finishing irradiation, the body 1 is taken out and the fast neutron reactor is filled again with a body 1 having a new capsule 7. COPYRIGHT: (C)1991,JPO | ||||||
| 138 | NUCLEAR REACTOR SYSTEM FOR EXTINGUISHING RADIOACTIVITY | US15759509 | 2016-12-14 | US20190115116A1 | 2019-04-18 | Osao SUMITA; Isao UENO; Takehiko YOKOMINE |
| Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container. | ||||||
| 139 | Charged particle acceleration device | US14379950 | 2013-02-25 | US10153059B2 | 2018-12-11 | Seth J. Putterman; Jonathan Hird; Brian Naranjo |
| A charged particle acceleration device according to some embodiments of the current invention includes a first triboelectric element, a second triboelectric element arranged proximate the first triboelectric element to be brought into contact with and separated from the first triboelectric element, an actuator assembly operatively connected to at least one of the first and second triboelectric elements to bring the first and second triboelectric elements into contact with each other and to separate the first and second triboelectric elements from each other, and a charged-particle source configured to provide charged particles in a gap between the first and second triboelectric elements. | ||||||
| 140 | RADIOISOTOPE PRODUCTION TARGET INSERT DESIGN AND TARGET HARVESTING METHODOLOGY FOR LONG TERM IRRADIATION IN COMMERCIAL NUCLEAR REACTORS | US15596024 | 2017-05-16 | US20180336975A1 | 2018-11-22 | Michael D. Heibel |
| A device and method that enables a specimen that is to be converted into a radioisotope to be inserted into an extended, retractable thimble of a nuclear reactor moveable in-core detector system and be harvested after irradiation either during reactor operation or a refueling outage without damaging the retractable thimble. The specimen is enclosed within the interior of a forward portion of a tubular member having a closed lead end and structured to travel within the retractable thimble. The tubular member is sized to extend from a position above and proximate the desired core elevation the specimen is to be irradiated at to a location above a seal table that the retractable thimble extends through. The specimen is inserted and withdrawn from the core by inserting or withdrawing the tubular member from above the seal table. Desirably, the forward end of the tubular member is divided into several specimen compartments. | ||||||
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