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公开(公告)号：US20240355488A1
公开(公告)日：2024-10-24
申请号：US18536193
申请日：2023-12-11
申请人： NuScale Power, LLC
发明人： Allyson Callaway , Ben Bristol , Kenneth Rooks , Larry Linik
IPC分类号： G21C7/12 , F22B35/00 , G21C1/02 , G21C7/08 , G21C7/22 , G21C7/24 , G21C9/02 , G21C9/033 , G21C13/02 , G21D1/00 , G21D3/02 , G21D3/14 , G21D3/16 , G21D3/18 , G21D5/08
CPC分类号： G21C7/12 , G21C7/22 , G21C9/033 , G21D3/14 , G21D3/16 , G21D3/18 , F22B35/004 , G21C1/028 , G21C7/08 , G21C7/24 , G21C9/02 , G21C13/022 , G21D1/006 , G21D3/02 , G21D5/08
摘要： A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction; a riser positioned above the reactor core; a primary coolant flow path that extends from a bottom portion of the volume through the reactor core and through an annulus between the riser and the reactor vessel; a primary coolant that circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to generate electric power in a power generation system; and a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.
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公开(公告)号：US12100523B2
公开(公告)日：2024-09-24
申请号：US17831083
申请日：2022-06-02
申请人： NuScale Power, LLC
发明人： Allyson Callaway , Ben Bristol , Kenneth Rooks , Larry Linik
IPC分类号： G21C7/22 , G21C7/12 , G21C9/033 , G21D3/14 , G21D3/16 , G21D3/18 , F22B35/00 , G21C1/02 , G21C7/08 , G21C7/24 , G21C9/02 , G21C9/027 , G21C13/02 , G21D1/00 , G21D3/02 , G21D5/08
CPC分类号： G21C7/12 , G21C7/22 , G21C9/033 , G21D3/14 , G21D3/16 , G21D3/18 , F22B35/004 , G21C1/028 , G21C7/08 , G21C7/24 , G21C9/02 , G21C13/022 , G21D1/006 , G21D3/02 , G21D5/08
摘要： A nuclear power system includes a reactor vessel that includes a reactor core mounted therein. The reactor core includes nuclear fuel assemblies configured to generate a nuclear fission reaction. The nuclear power system further includes a chemical injection system configured to inject a chemical into the reactor vessel and remove the chemical from the reactor vessel, and a control system communicably coupled to the chemical injection system and configured to control a power output of the nuclear fission reaction. For example, the control system can determine that the power output is greater than an upper value of a range or less than a lower value of the range and, based on the determination, adjust an amount of the chemical injected into or removed from the reactor vessel by the chemical injection system to adjust the power output.
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3.发明公开公开(公告)号：US20240233968A1
公开(公告)日：2024-07-11
申请号：US18406873
申请日：2024-01-08
申请人： Holtec International
发明人： Krishna P. SINGH , Indreash Rampall
CPC分类号： G21D1/006 , F01K7/16 , F05D2230/80
摘要： A power generation system and related method for repowering a fossil-fueled power plant using a carbon-free nuclear steam supply system (NSSS) which replaces the existing fossil plant steam generator which burns fossil fuel such as coal, oil, or natural gas. The existing fossil plant energy conversion system including the turbine-generator (turbogenerator) and auxiliary components of the Rankine cycle is retained. The NSSS may include a small modular reactor (SMR) unit comprising a reactor vessel with nuclear fuel core and steam generator which receives heated primary coolant from the reactor to produce main steam to operate the Rankine cycle. The main steam output by the SMR unit is compressed in a steam compressor to increase its pressure to a level necessary to operate the turbogenerator. The compressor may be operated via a portion of the main steam. An intercooler of the compressor may be used for main steam reheating.
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公开(公告)号：US12033765B2
公开(公告)日：2024-07-09
申请号：US17438960
申请日：2020-03-13
发明人： Young Hwan Hwang , Seok-Ju Hwang , Mi-Hyun Lee , Cheon-Woo Kim
CPC分类号： G21D1/003 , G08B21/182 , G21C9/04
摘要： A safety cover structure of a nuclear facility is disclosed. The safety cover structure includes: a cover portion rotatably installed on a body protection concrete slab to cover a cavity where a reactor pressure container is located; a driving portion configured to rotate the cover portion relative to the cavity; an opening and closing portion that is installed on the cover portion and is configured to allow materials resulting from cutting and dismantling of the reactor pressure container to move therethrough; a fire extinguishing portion configured to extinguish a fire generated inside the cover portion; a dose sensor installed in the cover portion and configured to measure a radiation dose emitted from the reactor pressure container; and an alarm portion configured to receive a sensing signal from the dose sensor and provide an alarm when the measured radiation dose exceeds a predetermined value.
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5.发明授权公开(公告)号：US11948700B2
公开(公告)日：2024-04-02
申请号：US17094850
申请日：2020-11-11
申请人： Grant Charters , Sudesh Aggarwal
发明人： Grant Charters , Sudesh Aggarwal
摘要： A method for collection of dry samples taken directly from a nuclear reactor core interior. Incremental samples of irradiated metal alloy components of the reactor core may be taken and collected in-situ using a specialized metal-cutting drill bit having a hollow tungsten carbide sampling cutting head, in conjunction with an angled sampling gantry. The drill bit body has an interior airflow passage in hermetic communication with a filter located in a glove box. Air holes are formed through a face of the cutting head. A vacuumed airflow through the airflow passage and at the cutting head causes a sample of any of metal chips, filings, and dust to be obtained directly from the reactor core by being pulled through the air holes and into the airflow passage and ultimately into the filter. A collected sample may be analyzed for radionuclides and radioactivity level.
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公开(公告)号：US20240025517A1
公开(公告)日：2024-01-25
申请号：US18480559
申请日：2023-10-04
CPC分类号： B63B35/44 , G21D1/00 , G21C11/04 , G21C15/18 , B63B2035/4446
摘要： Disclosed is an offshore energy generation system (OEGS) that eliminates greenhouse gas emissions during operation, mitigating earthquake and tsunami impacts, and nuclear meltdown safety. The OEGS comprises a floating facility configured for dynamic positioning to a target site via a system that is communicably coupled to the floating facility. The floating facility is coupled to seawater collection system; steam generation system; electric power generation system that uses at least one of: steam, nuclear fission, nuclear fusion or hydrogen fuel cells for generating electric power; ammonia, freshwater, nitrogen and hydrogen generation systems, cooling water system, electric power, freshwater, and ammonia export systems, multiple offshore cranes, living quarters and helideck; automation, control and safety system for controlling one or more components. The OEGS is effective, affordable and a reliable solution for climate change as it delivers clean energy in the form of electricity, ammonia and/or freshwater.
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公开(公告)号：US11879385B2
公开(公告)日：2024-01-23
申请号：US17170272
申请日：2021-02-08
发明人： Andrew J. Eifert
CPC分类号： F02C1/05 , F02C6/18 , F02C7/08 , F02C6/16 , F05D2220/50 , F05D2220/76 , G21D1/006 , G21D1/02 , G21D3/02
摘要： A power-generation system for a nuclear reactor includes a power unit, a reactor heat exchanger, and an auxiliary combustion system. The power unit produces compressed air that is heated by the reactor heat exchanger. The auxiliary combustion system includes an auxiliary combustor located external to the power unit and fluidly connected with the compressed air to increase the temperature of the compressed air.
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公开(公告)号：US11848113B2
公开(公告)日：2023-12-19
申请号：US16578335
申请日：2019-09-21
发明人： Charles Howard Cella
摘要： The systems and methods generally include a nuclear power plant unit assembled in a shipyard from a plurality of structural modules, each of the structural modules having manufactured components for use in power production when moored or fixed to a floor at least one of in and proximal to at least one of an offshore marine environment, a river environment and a coastal marine environment. The nuclear power plant unit is subdivided into at least one arrangement of structural modules that includes an electrical interface for one of transmitting electrical power generated by the nuclear unit and powering a system of the unit, a communications interface for communications internal or external to the unit, a user interface that is configured to permit a user to access a system of the unit, and a network interface for data communications to or from the unit.
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公开(公告)号：US11802686B2
公开(公告)日：2023-10-31
申请号：US17413547
申请日：2020-01-28
摘要： Reverse steam generator for a lead-cooled fast reactor. The reverse steam generator comprises a cylindrical body with a bundle of heat exchange tubes located inside, the ends of the heat exchange tubes being fixed in tube sheets with intermediate support grids; inlet and outlet spherical chambers for supplying liquid metal coolant; a lower branch pipe for inlet water; and an upper branch pipe for a steam outlet. The cylindrical body is arranged horizontally and is curved in a Z-shape with a difference in height. The bundle of heat exchange tubes is also made in a Z-shape, repeating the bend of the cylindrical body.
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公开(公告)号：US11699532B2
公开(公告)日：2023-07-11
申请号：US17131922
申请日：2020-12-23
申请人： BWXT Canada Ltd.
发明人： Kareem M. A. Aly
IPC分类号： F28D9/00 , G21C15/22 , F22B1/02 , F22B37/20 , F28D7/06 , F28F9/013 , G21C15/14 , G21C15/24 , G21C15/243 , G21D1/00
CPC分类号： G21C15/22 , F22B1/023 , F22B37/205 , F28D7/06 , F28F9/013 , G21C15/14 , G21C15/24 , G21C15/243 , G21D1/00
摘要： Arrangement for supporting U-bend tube sections in the high heat environment of steam generators using flat bars. The invention uses a combination of thicker and thinner flat bars to impart a serpentine path to the arc of the normally curvilinear U-tubes. The support system accommodates the dilation and contraction of coolant tubes and other elements caused by the extreme and varying conditions inside a steam generator, and which can cause gaps between coolant tubes and prior art tube support bars. Bars of alternating thickness provide alternating offsets to tensionally push and support each tube on multiple sides and in multiple locations, and this tension keeps the tubes in contact with at least some flat bars on multiple sides regardless of size and shape changes. Support arrangement includes a set of fan bars, each fan bar including thick and thin flat bars projecting up and out from a collector bar.
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