公开(公告)号：US20200072087A1

公开(公告)日：2020-03-05

申请号：US16613223

申请日：2018-05-14

Applicant: KOREA ATOMIC ENERGY RESEARCH INSTITUTE ,  KING ABDULLAH CITY FOR ATOMIC AND RENEWABLE ENERGY

Inventor： Youngin KIM ,  Youngmin BAE ,  Hunsik HAN ,  Cheongbong CHANG ,  Junewoo KEE ,  Minkyu LEE ,  Bonghyun CHO ,  Kisun PARK

IPC: F01K3/18 ,  F01K9/00 ,  F01K11/02 ,  G21C15/16 ,  G21D1/00 ,  G21D5/12

Abstract: An external reactor vessel cooling and electric power generation system according to the present invention includes an external reactor vessel cooling section formed to enclose at least part of a reactor vessel with small-scale facilities so as to cool heat discharged from the reactor vessel, a power production section including a small turbine and a small generator to generate electric energy using a fluid that receives heat from the external reactor vessel cooling section, a condensation heat exchange section 140 to perform a heat exchange of the fluid discharged after operating the small turbine, and condense the fluid to generate condensed water, and a condensed water storage section to collect therein the condensed water generated in the condensation heat exchange section, wherein the fluid is phase-changed into gas by the heat received from the reactor vessel. The external reactor vessel cooling and electric power generation system according to the present invention can continuously operate even during an accident as well as during a normal operation to cool the reactor vessel and produce emergency power, thereby enhancing system reliability. The external reactor vessel cooling and electric power generation system according to the present invention can easily apply safety class or seismic design using small-scale facilities, and its reliability can be improved owing to applying the safety class or seismic design.

公开(公告)号：US20190203614A1

公开(公告)日：2019-07-04

申请号：US15857532

申请日：2017-12-28

Applicant: GE-Hitachi Nuclear Energy Americas LLC

Inventor： Eric P. Loewen ,  Scott E. Rasmussen

IPC: F01K7/38 ,  G21D5/16 ,  F22B1/02 ,  G21D5/12 ,  F01K7/34 ,  F01K7/44 ,  F01K11/02 ,  F01K19/00

CPC classification number: F01K7/38 ,  F01K7/345 ,  F01K7/44 ,  F01K11/02 ,  F01K19/00 ,  F22B1/023 ,  G21D5/12 ,  G21D5/16

Abstract: Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators includes one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.

公开(公告)号：US20160189810A1

公开(公告)日：2016-06-30

申请号：US14587226

申请日：2014-12-31

Applicant: Adrian M. MISTREANU ,  James Scott BOWMAN ,  Phillip Glen ELLISON ,  John S. BENNION ,  Bulent ALPAY

Inventor： Adrian M. MISTREANU ,  James Scott BOWMAN ,  Phillip Glen ELLISON ,  John S. BENNION ,  Bulent ALPAY

IPC: G21C15/16 ,  G21D5/12 ,  B04C1/00 ,  F16T1/34 ,  B01D45/16

CPC classification number: G21C15/16 ,  B01D45/16 ,  F01K5/00 ,  F22B37/268 ,  Y02E30/31

Abstract: In one embodiment, the steam separator includes a standpipe configured to receive a gas-liquid two-phase flow stream, and a first swirler configured to receive the gas-liquid two-phase flow stream from the standpipe. The first swirler is configured to separate the gas-liquid two-phase flow stream. The first swirler includes a direct flow portion and an indirect flow portion. The direct flow portion has a direct flow channel for permitting direct flow of the gas-liquid two-phase flow stream through the first swirler, and the indirect flow portion has at least one indirect flow channel defined by at least one vane in the first swirler for providing an indirect flow of the gas-liquid two-phase flow stream through the first swirler.

Abstract translation: 在一个实施例中，蒸汽分离器包括配置成接收气液两相流动流的立管和被配置为从立管接收气液两相流动流的第一旋流器。 第一旋流器构造成分离气液两相流动流。 第一旋流器包括直流部分和间接流动部分。 直接流动部分具有直接流动通道，用于允许气液两相流动流直接流过第一旋流器，并且间接流动部分具有由第一旋流器中的至少一个叶片限定的至少一个间接流动通道 用于提供通过第一旋流器的气液两相流的间接流动。

公开(公告)号：US4585053A

公开(公告)日：1986-04-29

申请号：US414440

申请日：1982-09-02

Applicant: Jay S. Kaufman ,  John A. Kissinger

Inventor： Jay S. Kaufman ,  John A. Kissinger

IPC: G21D5/12 ,  F28D7/00 ,  F28D7/10 ,  F28D7/12 ,  F28D7/16 ,  F28F9/22 ,  G21D1/00 ,  G21D5/08

CPC classification number: F28D7/106 ,  F28F9/0136 ,  F28D2021/0054 ,  F28D7/1661 ,  F28F2009/226 ,  F28F2275/14 ,  Y10S165/409

Abstract: A compact bayonet tube type heat exchanger which finds particular application as an auxiliary heat exchanger for transfer of heat from a reactor gas coolant to a secondary fluid medium. The heat exchanger is supported within a vertical cavity in a reactor vessel intersected by a reactor coolant passage at its upper end and having a reactor coolant return duct spaced below the inlet passage. The heat exchanger includes a plurality of relatively short length bayonet type heat exchange tube assemblies adapted to pass a secondary fluid medium therethrough and supported by primary and secondary tube sheets which are releasibly supported in a manner to facilitate removal and inspection of the bayonet tube assemblies from an access area below the heat exchanger. Inner and outer shrouds extend circumferentially of the tube assemblies and cause the reactor coolant to flow downwardly internally of the shrouds over the tube bundle and exit through the lower end of the inner shroud for passage to the return duct in the reactor vessel.

Abstract translation: 一种紧凑型卡口式管式热交换器，其特别用作辅助热交换器，用于将热量从反应器气体冷却剂转移到次级流体介质。 热交换器被支撑在反应堆容器中的垂直空腔内，反应堆容器在其上端与反应堆冷却剂通道相交并且具有在入口通道下方隔开的反应堆冷却剂返回管道。 热交换器包括多个相对较短长度的卡口式热交换管组件，其适于使二次流体介质通过其中并由主管和辅助管板支撑，该管和第二管板以可释放的方式支撑，以便于将卡口管组件从 热交换器下方的通道区域。 内部和外部护罩在管组件的周向延伸并且使得反应堆冷却剂在护罩的内部向下流过管束并且通过内护罩的下端离开，以通过反应堆容器中的返回管道。

公开(公告)号：US4236970A

公开(公告)日：1980-12-02

申请号：US877741

申请日：1978-02-14

Applicant: Elmar Harand ,  Eberhard Michel

Inventor： Elmar Harand ,  Eberhard Michel

IPC: F22B1/16 ,  F22B1/02 ,  G21C1/08 ,  G21D1/04 ,  G21D5/12 ,  G21C13/02

CPC classification number: G21D1/04 ,  F22B1/023 ,  Y02E30/40

Abstract: A coolant pump and a steam generator are formed together into a structural unit, the steam generator being a straight-tube steam generator having a central ascending pipe, a tube bundle having a central passageway through which the ascending pipe extends, an upper primary-side inlet, chamber communicating with the tube bundle at an upper end thereof, a lower primary chamber communicating with the tube bundle at a lower end thereof, the central ascending pipe communicating with the inlet chamber for feeding primary medium thereto from which the primary medium flows back through the tube bundle to the lower primary chamber, the ascending pipe having an axial elongation, the coolant pump having an impeller and a guidance device surrounding the impeller, the ascending pipe-elongation having a construction corresponding to that of the guidance device, partition means for dividing the lower primary chamber into a suction space and an outlet chamber space, the pump having a suction side connected through the suction space of the lower primary chamber to a hot line string of a double line connected to the steam generator, the outlet chamber space of the lower primary chamber being connected to a cold line string of the double line.

Abstract translation: 冷却剂泵和蒸汽发生器一起形成结构单元，蒸汽发生器是具有中央上升管的直管蒸汽发生器，管束具有上升管延伸穿过的中心通道，上部一次侧 入口室在其上端与管束连通，下主单元在其下端与管束连通，中央上升管与入口室连通，用于向其供应主介质，主介质从该入口室流回 通过管束到下部主室，上升管具有轴向伸长，冷却剂泵具有叶轮和围绕叶轮的引导装置，上升管伸长具有对应于引导装置的构造，分隔装置 为了将下部主室分成吸入空间和出口室空间，泵具有吸入侧连接件 通过下部主室的吸入空间连接到连接到蒸汽发生器的双线的热线串，下部主室的出口室空间连接到双线的冷线串。

公开(公告)号：US3153620A

公开(公告)日：1964-10-20

申请号：US13287761

申请日：1961-08-21

Applicant: SULZER AG

Inventor： PAUL PROFOS

IPC: G21D5/12

CPC classification number: G21D5/12

公开(公告)号：US20230162879A1

公开(公告)日：2023-05-25

申请号：US17991837

申请日：2022-11-21

Applicant: NuScale Power, LLC

Inventor： Tamas R. Liszkai ,  Todd Sorensen

IPC: G21D5/12 ,  F22B37/00

CPC classification number: G21D5/12 ,  F22B37/002

Abstract: Steam generator systems including tubesheet assemblies, such as for use in nuclear reactor systems, and associated devices and methods are described herein. A representative steam generator system can be installed in a nuclear reactor vessel positioned to house a primary coolant. The steam generator system can include a tubesheet assembly defining a plenum and comprising a tubesheet and a flexible connection portion coupling the tubesheet to the reactor vessel. The tubesheet can include a plurality of perforations fluidly coupled to the plenum. The steam generator system can further comprise a plurality of heat transfer tubes fluidly coupled to the perforations and configured to receive a flow of a secondary coolant. The connection portion can be more flexible than the tubesheet and the reactor vessel to reduce stresses on the tubesheet and the connections (e.g., tube-to-tubesheet (TTS) welds) between the tubes and the tubesheet during operation of the nuclear reactor system.

公开(公告)号：US20230096162A1

公开(公告)日：2023-03-30

申请号：US18072592

申请日：2022-11-30

Applicant: GE-Hitachi Nuclear Energy Americas LLC

Inventor： Eric P. Loewen ,  Scott E. Rasmussen

IPC: F01K7/38 ,  G21D5/16 ,  F22B1/02 ,  F01K19/00 ,  F01K7/34 ,  F01K7/44 ,  F01K11/02 ,  G21D5/12 ,  G21D1/00

Abstract: Steam generators in power plants exchange energy from a primary medium to a secondary medium for energy extraction. Steam generators include one or more primary conduits and one or more secondary conduits. The conduits do not intermix the mediums and may thus discriminate among different fluid sources and destinations. One conduit may boil feedwater while another reheats steam for use in lower and higher-pressure turbines, respectively. Valves and other selectors divert steam and/or water into the steam generator or to other turbines or the environment for load balancing and other operational characteristics. Conduits circulate around an interior perimeter of the steam generator immersed in the primary medium and may have different cross-sections, radii, and internal structures depending on contained. A water conduit may have less flow area and a tighter coil radius. A steam conduit may include a swirler and rivulet stopper to intermix water in any steam flow.

公开(公告)号：US11282613B2

公开(公告)日：2022-03-22

申请号：US16733497

申请日：2020-01-03

Applicant: GENERAL ELECTRIC COMPANY

Inventor： Narendra Digamber Joshi ,  James William Bray

IPC: G21D5/12 ,  F22B1/18 ,  F01K11/02 ,  F02C1/10 ,  F02C1/05 ,  F02C6/02 ,  F02C3/00 ,  F02C9/24 ,  F02C9/18

Abstract: A turbine engine comprising a compressor section and a turbine section in serial flow arrangement defining a working air flow path with a heat exchanger in fluid communication the working air flow path, and a nuclear fuel in thermal communication with the heat exchanger and a release valve in fluid communication with the working air flow path.

公开(公告)号：US4713209A

公开(公告)日：1987-12-15

申请号：US852315

申请日：1986-04-15

Applicant: Hitoshi Ishimaru ,  Toshiki Kobayashi

Inventor： Hitoshi Ishimaru ,  Toshiki Kobayashi

IPC: F22D1/32 ,  G21D1/02 ,  G21D5/12 ,  G21C7/32

CPC classification number: G21D5/12 ,  G21D1/02 ,  Y02E30/40

Abstract: A drain recovery system for the condensate feedwater system of a nuclear power plant having condensate pumps for boosting the condensate from a condenser, and feedwater heaters for heating the condensate from the condensate pumps. The drain recovery system is provided with drain pumping-up recovery having a drain tank for storing a feedwater heater drain, and drain pumps connected to the drain tank for pumping up the drain therein to inject it into said condensate feedwater system at a predetermined portion thereof, and drain level control device having a conduit connected between a portion of the drain pumping-up recovery system upstream of the drain pumps and a portion of the condensate feedwater system upstream of the condensate pumps for causing the drain in the drain tank to be returned to the portion upstream of the condensate pumps by a pressure differential therebetween so as to maintain a drain level in the drain tank at a predetermined position when the plant operates at a low load level or the drain pumps malfunction.

Abstract translation: 用于具有用于从冷凝器提升冷凝物的冷凝水泵的核电站的冷凝水给水系统的排水回收系统以及用于从冷凝水泵加热冷凝物的给水加热器。 排水回收系统具有排水排空回收装置，其具有用于储存给水加热器排水的排水箱，以及连接到排水箱的排水泵，用于向其排出排水口，以将其排出到其预定部分的所述冷凝水给水系统 和排水平面控制装置，其具有连接在排水泵上游的排水泵送回收系统的一部分和冷凝水泵上游的冷凝物给水系统的一部分之间的导管，用于使排水箱中的排水口返回 通过它们之间的压力差到冷凝水泵的上游部分，以便当设备在低负载水平下操作或排水泵故障时，将排水槽中的排放水平保持在预定位置。