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公开(公告)号：US11935661B2
公开(公告)日：2024-03-19
申请号：US17399859
申请日：2021-08-11
CPC分类号： G21C21/02 , G21C3/64 , B22F3/15 , B22F2301/20 , B64G1/408 , C22C1/05 , F02K7/02 , G21C5/02 , G21C5/12
摘要： CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.
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公开(公告)号：US11875906B2
公开(公告)日：2024-01-16
申请号：US17950830
申请日：2022-09-22
发明人： David Leblanc
IPC分类号： G21C17/10 , G21C1/22 , G21C1/32 , G21D3/00 , G21D9/00 , G21C5/02 , G21C17/112 , G21C19/28 , G21D1/00
CPC分类号： G21C1/22 , G21C1/322 , G21D3/00 , G21D9/00 , G21C5/02 , G21C17/112 , G21C19/28 , G21D1/00 , Y02E30/30
摘要： The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.
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公开(公告)号：US20230132031A1
公开(公告)日：2023-04-27
申请号：US17914019
申请日：2021-03-23
发明人： Lance Snead , Jason Trelewicz
IPC分类号： G21C11/02 , C04B35/053 , G21F1/08 , G21C5/02 , G21C5/12
摘要： A composite structure is disclosed comprising a neutron-absorbing metal hydride phase contained within a matrix having a density of greater than 95%. In various embodiments the metal hydride is a hydride of one or more of the following: Gadolinium, Hafnium, Europium, Samarium. The composite structure is utile as a shield for fusion or fission reactors.
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公开(公告)号：US11605472B2
公开(公告)日：2023-03-14
申请号：US17833530
申请日：2022-06-06
申请人： BK Clean Energy LLC
摘要： A closed-vessel molten salt reactor (cvMSR) is described herein. A cvMSR may comprise a suspended container, such as a metallic container, within a trench surrounded by a concrete enclosure and a concrete cover having a number of channels. The suspended container may be hollow and a solution of fissile materials and salt materials may be provided within the suspended container. The solution may be capable of undergoing a chain reaction nuclear fission process once a threshold temperature is reached. Heat generated by the solution may heat a fluid surrounding the suspended container. The heated fluid may be transported, through the number of channels of the concrete cover, to an external location where the heated fluid may be used in distributing heat and/or electricity generation.
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公开(公告)号：US20220375636A1
公开(公告)日：2022-11-24
申请号：US17880319
申请日：2022-08-03
发明人： Dalin Zhang , Dianqiang Jiang , Xinyu Li , Xin Min , Chenglong Wang , Wenxi Tian , Suizheng Qiu , Guanghui Su
摘要： A multipurpose small modular fluoride-salt-cooled high-temperature reactor energy system includes: a reactor body system, a passive residual heat removal system, a compact supercritical carbon dioxide Brayton cycle system, a secondary loop system, and a comprehensive utilization supercritical carbon dioxide Brayton cycle system. Nuclear reactor adopts helical cruciform fuel and graphite matrix material filled with TRISO element, which can improve heat transfer performance and inherent safety. Thermal efficiency of the compact supercritical carbon dioxide Brayton cycle system is above 48%, which can be used in places with limited space. Thermal efficiency of the comprehensive utilization supercritical carbon dioxide Brayton cycle system is above 54%, which can be applied to places with abundant resources. The present invention not only realizes efficient and compact utilization of energy, but also meets the needs of multiple purposes, integrated production, storage and conversion of energy.
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公开(公告)号：US11476011B2
公开(公告)日：2022-10-18
申请号：US16627738
申请日：2018-12-25
申请人： Joint Stock Company “State Scientific Centre of the Russian Federation—Institute for Physics and Power Engineering named after A.I. Leypunsky” , Joint Stock Company «Science and Innovations»
IPC分类号： G21C15/257 , G21C1/12 , G21C5/02 , G21C3/40 , G21C5/12
摘要： The reactor core includes at least one module, a solid neutron moderator, and a liquid neutron moderators. Each module contains a casing, at least one heat pipe, one fuel element and thermal insulation. The heat pipe comprises a casing, a wick, and a coolant. The fuel element is made of nuclear fuel, arranged along an evaporation area of the heat pipe, around the heat pipe casing, in thermal contact with the heat pipe casing, and enclosed in a can. Liquid metals are used as the coolant of the heat pipe. Thermal insulation is arranged between the can and the module casing. At least one hole is made in the solid neutron moderator. Each module is arranged within a respective hole of the solid neutron moderator. The space between the module casing and the solid neutron moderator is filled with a liquid neutron moderator.
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公开(公告)号：US11469005B2
公开(公告)日：2022-10-11
申请号：US16627737
申请日：2018-12-25
申请人： JOINT STOCK COMPANY “STATE SCIENTIFIC CENTRE OF THE RUSSIAN FEDERATION—INSTITUTE FOR PHYSICS AND POWER ENGINEERING NAMED AFTER A.I. LEYPUNSKY” , JOINT STOCK COMPANY “SCIENCE AND INNOVATIONS”
摘要： A nuclear reactor core includes at least one module, a solid neutron moderator, and liquid neutron moderator. Each module comprises a housing, at least one heat pipe, at least one fuel element, casing, and thermal insulation. The heat pipe comprises a housing, wick, and evaporating coolant. The fuel element includes a shell and nuclear fuel. An evaporation zone of the heat pipe and the fuel elements are enclosed by the casing. The casing is filled with a liquid coolant. Liquid metal, for example, lithium, calcium, lead, and/or silver, is used as the heat pipe coolant and the liquid coolant. The thermal insulation is arranged in a space between the casing and module housing. The solid neutron moderator has at least one hole, wherein at least one module is located. A space between the solid neutron moderator and module is filled with the liquid neutron moderator.
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8.发明申请公开(公告)号：US20220068512A1
公开(公告)日：2022-03-03
申请号：US17521955
申请日：2021-11-09
发明人： William E. RUSSELL, II , Joshua J. BERGMAN , Jonathan W. CIRTAIN , Craig D. GRAMLICH , James B. INMAN , Matthew P. LEVASSEUR , Joseph K. MILLER , Ryan Z. ZIEGLER
摘要： Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.
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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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公开(公告)号：US10283223B2
公开(公告)日：2019-05-07
申请号：US14859100
申请日：2015-09-18
发明人： M. Sheldon Hansen
IPC分类号： G21C1/14 , G21C1/16 , G21C1/22 , G21C5/02 , G21C19/14 , G21C19/19 , G21C11/06 , G21C5/12 , G21D9/00
摘要： Systems and methods for providing a molten salt reactor can include a graphite reactor core that defines an internal space, with multiple fuel wedges being received in the internal space, and with the wedges each defining a fuel channel extending from a first end to a second end of each of the wedges. The reactor can further include a fuel pin rod that defines an internal fuel conduit and that is disposed between at least two of the wedges. The reactor core can also define a fuel ingress port and a fuel egress port. The reactor core can further be rotatably received within a reactor housing such that the ports are configured to become at least one of more occluded and less occluded as the reactor core rotates.
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