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1.发明公开公开(公告)号：US20240304349A1
公开(公告)日：2024-09-12
申请号：US18543260
申请日：2023-12-18
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：US12040098B2
公开(公告)日：2024-07-16
申请号：US17297036
申请日：2019-11-27
摘要： A closed loop heat convection cooling system for nuclear reactors. The cooling system is formed outside the containment structure of the nuclear reactor. The cooling system has cooling assemblies that are housed in protective structures, which shield the cooling assemblies from projectile impact. Air inlet and outlet apertures are formed in the protective structures to cause outside air to be drawn into the protective structures to passively cool the cooling assemblies.
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公开(公告)号：US12031676B2
公开(公告)日：2024-07-09
申请号：US16828723
申请日：2020-03-24
发明人： Jon Craig , Michael Basic
CPC分类号： F17C1/12 , B01J2219/00155 , G21C11/08 , G21C13/02 , Y02E30/30
摘要： Systems and methods for insulating vessels are disclosed. In one or more embodiments, the disclosure provides a vessel insulation system (e.g., for use with a reactor or pressure vessel), which includes a floating ring sized to circumscribe a top nozzle of a vessel; a plurality of straps connected to the floating ring, the plurality of straps extending downward from the floating ring and being positioned to run along a length of the outer shell of the vessel; and a plurality of segmented rings positioned to circumscribe the outer shell of the vessel and connected to the plurality of straps. The plurality of segmented rings is configured to support an insulation material circumscribing the outer shell of the vessel, which can provide effective securement of the insulation material around the outer shell without welding components on the vessel to secure the insulation material.
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公开(公告)号：US11935663B2
公开(公告)日：2024-03-19
申请号：US17081753
申请日：2020-10-27
申请人： SMR Inventec, LLC
IPC分类号： G21C7/12 , G21C7/10 , G21C7/117 , G21C9/004 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/10 , G21D1/00
CPC分类号： G21C7/12 , G21C7/10 , G21C7/117 , G21C9/004 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/10 , G21D1/00 , G21D1/006 , Y02E30/30
摘要： A control rod drive system (CRDS) for use in a nuclear reactor. In one embodiment, the system generally includes a drive rod mechanically coupled to a control rod drive mechanism (CRDM) operable to linearly raise and lower the drive rod along a vertical axis, a rod cluster control assembly (RCCA) comprising a plurality of control rods insertable into a nuclear fuel core, and a drive rod extension (DRE) releasably coupled at opposing ends to the drive rod and RCCA. The CRDM includes an electromagnet which operates to couple the CRDM to DRE. In the event of a power loss or SCRAM, the CRDM may be configured to remotely uncouple the RCCA from the DRE without releasing or dropping the drive rod which remains engaged with the CRDM and in position.
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公开(公告)号：US20230112687A1
公开(公告)日：2023-04-13
申请号：US17632394
申请日：2020-10-04
IPC分类号： G21C11/06 , G21C3/62 , G21C13/02 , G21C7/24 , C04B35/563 , C04B35/117 , C04B35/575 , C04B35/626 , C04B35/645
摘要： To reduce size and mass of a nuclear reactor system, an integrated in-vessel shield separates the role of a neutron reflector and a neutron shield. Nuclear reactor system includes a pressure vessel including an interior wall and a nuclear reactor core located within the interior wall of the pressure vessel. Nuclear reactor core includes a plurality of fuel elements and at least one moderator element. Nuclear reactor system includes a reflector located inside the pressure vessel that includes a plurality of reflector blocks laterally surrounding the plurality of fuel elements and the at least one moderator element. Nuclear reactor system includes the in-vessel shield located on the interior wall of the pressure vessel to surround the reflector blocks. In-vessel shield is formed of two or more neutron absorbing materials. The two more neutron absorbing materials include a near black neutron absorbing material and a gray neutron absorbing material.
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公开(公告)号：US11525717B2
公开(公告)日：2022-12-13
申请号：US16863544
申请日：2020-04-30
发明人： Eric P. Loewen , James P. Sineath , Dean D. Molinaro , William C. Dawn , William J. Garcia , Oscar L. Meek , Patrick K. Day
IPC分类号： G01F1/66 , G21C17/032 , G21C17/10 , G01F1/325 , G21C13/02
摘要： Vibration-based flowmeters are useable in inaccessible nuclear reactor spaces. Pipe-organ-type flowmeters include a passage with an opening constricted, and subsequent widening section. An extension and outlet that create turbulence in the flow at the outlet create a standing wave and vibration in the extension and/or entire flowmeter. A flow rate of the fluid through the flowmeter can be calculated using length of the passage and/or known properties of the fluid. Multiple flowmeters of customized physical properties and types are useable together.
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7.发明授权公开(公告)号：US11482346B2
公开(公告)日：2022-10-25
申请号：US16989376
申请日：2020-08-10
申请人： NuGen, LLC
IPC分类号： G21D5/02 , G21C13/02 , F02C1/05 , G21C13/024 , G21C15/12 , G21C15/253 , G21D1/02 , G21D5/06 , F04D17/10 , F04D19/00
摘要： Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.
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公开(公告)号：US11120921B2
公开(公告)日：2021-09-14
申请号：US16665557
申请日：2019-10-28
IPC分类号： G21C19/32 , G21D1/02 , G21C3/04 , G21C11/08 , G21C13/02 , G21C15/12 , G21C15/18 , G21C19/20 , G21C19/07
摘要： A method and apparatus for extending the period a nuclear steam supply system spent fuel pool can be safely passively cooled by storing the spent fuel offloaded from the reactor, in the containment for one reactor operating cycle. During a refueling the spent fuel that is not to be returned to the reactor and the spent fuel that will be returned to the reactor are stored separately in shielded locations within the containment. After one operating cycle, the spent fuel stored within the containment that was not returned to the reactor just prior to the last operating cycle, is offloaded to the spent fuel pool and replaced by the newly offloaded spent fuel that is being retired.
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公开(公告)号：US11062811B2
公开(公告)日：2021-07-13
申请号：US15945612
申请日：2018-04-04
申请人： NuScale Power, LLC
发明人： Tamas Liszkai , Seth Cadell , Alex Kruskamp , Matthew Mallet
摘要： A thermal control system for a reactor pressure vessel comprises a plate having a substantially circular shape that is attached to a wall of the reactor pressure vessel. The plate divides the reactor pressure vessel into an upper reactor pressure vessel region and a lower reactor pressure vessel region. Additionally, the plate is configured to provide a thermal barrier between a pressurized volume located within the upper reactor pressure vessel region and primary coolant located within the lower reactor pressure vessel region. One or more plenums provide a passageway for a plurality of heat transfer tubes to pass fluid through the wall of the reactor pressure vessel. The plurality of heat transfer tubes are connected to the plate.
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公开(公告)号：US10937555B2
公开(公告)日：2021-03-02
申请号：US14607760
申请日：2015-01-28
发明人： Chafik El Kabali , Hans Felser , Peter Hausch , Claus Schweinheim
摘要： The invention relates to a nuclear power plant including a containment vessel including a reactor pressure vessel for receiving fissionable nuclear fuel, an aerosol filter stage a pressure relief conduit through which a gas volume flow which is filtered in the aerosol filter stage is releasable to ambient through a pass through opening in the containment vessel, and an iodine filter stage through which the gas volume flow that is filtered in the aerosol filter stage is filterable before being released to the ambient, wherein the iodine filter stage is arranged within the containment vessel, characterized in that the aerosol filter stage and the iodine filter stage are connected with one another so that transferring the gas volume flow from the aerosol filter stage to the iodine filter stage is performed essentially at an identical pressure level.
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