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公开(公告)号：US11810681B2
公开(公告)日：2023-11-07
申请号：US18155193
申请日：2023-01-17
发明人： Yuriy Aleshin , Stuart Kellner
IPC分类号： G21C5/08 , G21C5/10 , G21C11/06 , G21C7/28 , G21C15/257
CPC分类号： G21C5/08 , G21C5/10 , G21C7/28 , G21C11/06 , G21C15/257
摘要： A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.
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公开(公告)号：US11791057B2
公开(公告)日：2023-10-17
申请号：US17368576
申请日：2021-07-06
申请人： TerraPower, LLC
摘要： A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.
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公开(公告)号：US20230298773A1
公开(公告)日：2023-09-21
申请号：US17864311
申请日：2022-07-13
申请人： Korea Advanced Institute of Science and Technology , IUCF-HYU (Industry-University Corporation Foundation Hanyang University)
发明人： Yong Hee KIM , Sung Joong KIM , Won Jun CHOI , Juhyeong LEE , Seongdong JANG , Taesuk OH , Eunhyug LEE
摘要： The present invention relates to a molten salt-metal reactor for implementing a micro-reactor, and more specifically, to a molten salt-metal reactor including a liquid metal nuclear fuel and a molten salt coolant, wherein the molten salt coolant is disposed in an upper portion of the liquid metal nuclear fuel such that the heat generated from the nuclear fuel is transferred to the molten salt coolant and cooled.
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公开(公告)号：US11742098B2
公开(公告)日：2023-08-29
申请号：US17156977
申请日：2021-01-25
发明人： Yuriy Aleshin , Stuart Kellner
IPC分类号： G21C5/10 , G21C5/08 , G21C11/06 , G21C7/28 , G21C15/257
CPC分类号： G21C5/10 , G21C5/08 , G21C7/28 , G21C11/06 , G21C15/257
摘要： A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.
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公开(公告)号：US11728052B2
公开(公告)日：2023-08-15
申请号：US17387320
申请日：2021-07-28
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, Jr. , Francesco Deleo , Michael J. Edwards , Gregory T. Markham , James A. Roecker , Noor Ullah , Daniel J. Walter , Kent E. Wardle
IPC分类号： G21C15/12 , G21C3/54 , G21C11/06 , G21C15/243
CPC分类号： G21C15/12 , G21C3/54 , G21C11/06 , G21C15/243
摘要： Alternative designs for a modular test reactor are presented. In one aspect, a molten fuel salt nuclear reactor includes a vessel defining a reactor volume, the vessel being open-topped and otherwise having no penetrations. A neutron reflector is provided within the vessel and displacing at least some of the reactor volume, the neutron reflector defining a reactor core volume. A plurality of heat exchangers are contained within the vessel above the neutron reflector. A flow guide assembly is provided within the neutron reflector that includes a draft tube draft tube separating a central portion of the reactor core volume from an annular downcomer duct. Fuel salt circulates from the reactor core volume, through the heat exchangers, into the downcomer duct and then back into the reactor core volume.
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公开(公告)号：US11488731B2
公开(公告)日：2022-11-01
申请号：US17080332
申请日：2020-10-26
申请人： TerraPower, LLC
发明人： Ryan Abbott , Anselmo T. Cisneros, Jr. , Daniel Flowers , Charles Gregory Freeman , Mark A. Havstad , Kevin Kramer , Jeffery F. Latkowski , Jon D. McWhirter , John R. Suyes, III
摘要： This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.
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公开(公告)号：US11145424B2
公开(公告)日：2021-10-12
申请号：US16264112
申请日：2019-01-31
申请人： TerraPower, LLC
发明人： Ryan Abbott , Anselmo T. Cisneros , Kevin Kramer , James A. Roecker , Daniel J. Walter , Kent E. Wardle
IPC分类号： G21C1/32 , G21C3/44 , G21C19/04 , G21C1/22 , G21C7/30 , G21C19/28 , F22B37/00 , G21C1/03 , G21C15/18 , G21C3/54 , G21D1/00 , G21D1/04 , G21C11/06
摘要： A molten chloride fast reactor (MCFR) includes a plurality of reflectors defining a central core having a core geometric center. A flow channel fluidically connected to the central core. The flow channel includes an outlet flow channel downstream of the central core and an inlet flow channel upstream from the central core. A primary heat exchanger (PHX) disposed outside the central core and between the outlet flow channel and the inlet flow channel. The MCFR also includes a decay heat heat exchanger (DHHX). At least a portion of the DHHX is disposed above the core geometric center, and a fuel salt is configured to circulate at least partially through the outlet flow channel, the DHHX, the PHX, the inlet flow channel, and the central core.
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公开(公告)号：US11050094B1
公开(公告)日：2021-06-29
申请号：US16039770
申请日：2018-07-19
申请人： UT-Battelle, LLC
发明人： Sheng Dai , Carter W. Abney , Richard T. Mayes , Dmitriy Dolzhnikov , Huimin Luo
IPC分类号： H01M10/39 , C07D307/68 , G21C3/54 , G21C1/02 , G21C11/06
摘要： A heat transfer (exchange) composition comprising a halide salt matrix having dispersed therein nanoparticles comprising elemental carbon in the absence of water and surfactants, wherein said halide is fluoride or chloride, wherein the halide salt may be an alkali halide salt (e.g., lithium fluoride, sodium fluoride, potassium fluoride, rubidium fluoride, sodium chloride, potassium chloride, rubidium chloride, and eutectic mixtures thereof) or an alkaline earth halide salt (e.g., fluoride or chloride salt of beryllium, magnesium, calcium, strontium, or barium), and wherein the nanoparticles comprising elemental carbon may be solid or hollow, and wherein the composition may further include nanoparticles comprising a fissile material (e.g., U, Th, or Pu) dispersed within the composition. Molten salt reactors (MSRs) containing these heat transfer compositions in coolant loops in thermal exchange with a reactor core, as well operation of such MSRs, are also described.
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公开(公告)号：US10395787B2
公开(公告)日：2019-08-27
申请号：US15759509
申请日：2016-12-14
申请人： CLEAR INC.
发明人： Osao Sumita , Isao Ueno , Takehiko Yokomine
摘要： 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.
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公开(公告)号：US10283224B2
公开(公告)日：2019-05-07
申请号：US15610124
申请日：2017-05-31
申请人： M. Sheldon Hansen
发明人： M. Sheldon Hansen
IPC分类号： G21C1/16 , G21C1/22 , G21C3/10 , G21C3/32 , G21C3/54 , G21C5/02 , G21C5/12 , G21C7/00 , G21D7/00 , G21C11/06 , G21C19/14 , G21C19/19 , G21C3/336 , G21D9/00
摘要： Systems and methods for providing and using molten salt reactors are described. While the systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). Other implementations are also described.
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