Water-spray residual heat removal system for nuclear power plant
    1.
    发明授权
    Water-spray residual heat removal system for nuclear power plant 有权
    核电站喷水剩余除热系统

    公开(公告)号:US09478318B2

    公开(公告)日:2016-10-25

    申请号:US13614898

    申请日:2012-09-13

    CPC classification number: G21C15/18 G21C19/28 G21D1/02 Y02E30/40

    Abstract: A residual heat removal system for a nuclear power plant. The residual heat removal system for a nuclear power plant may include an air duct provided on an outside of a reactor containment building, a heat exchanger disposed on an inside of the air duct, a first pipe to transfer, to the heat exchanger, steam generated in a steam generator disposed on an inside of the reactor containment building, and second pipe to transfer, to the steam generator, water condensation that is cooled and condensed in the heat exchanger, wherein the heat exchanger is air-cooled using outside air flowing inside of the air duct.

    Abstract translation: 一个用于核电站的剩余散热系统。 用于核电站的剩余散热系统可以包括设置在反应堆容纳建筑物的外部的空气管道,设置在空气管道内侧的热交换器,将热交换器传送到热交换器的第一管道 在设置在反应堆容纳建筑物的内部的蒸汽发生器中,以及第二管道,用于将热交换器中冷却和冷凝的水冷凝物传递到蒸汽发生器,其中,热交换器使用在内部流动的外部空气进行空气冷却 的风道。

    Pressurized light water reactor having flow converting grooves for emergency core cooling water
    3.
    发明授权
    Pressurized light water reactor having flow converting grooves for emergency core cooling water 有权
    具有用于应急芯冷却水的流动转换槽的加压轻水反应器

    公开(公告)号:US06928133B2

    公开(公告)日:2005-08-09

    申请号:US10606411

    申请日:2003-06-25

    Abstract: A direct vessel injection-type pressurized light water reactor (DVI-PLWR), in which an emergency core cooling water (ECC) is directly injected into a downcomer of a reactor vessel, is disclosed. In order to reduce the ratio of ECC bypass from the downcomer to a broken area of a cold leg in the case of a cold leg guillotine break (CLGB), such as a double-ended guillo4tine break (DEGB), a plurality of corrugations, having a V-shaped cross-section, are vertically arranged around each of the inner surface of a pressure vessel and the outer surface of a core barrel at regular intervals, with a vertical groove formed between two neighboring corrugations. The grooves phase-separate the ECC from a high-speed lateral flow of fluid running in the downcomer, and the separated ECC stagnates in the form of vortexes in the grooves, prior to flowing down to the lower section of the downcomer due to gravity. The DVI-PLWR thus reduces the ratio of ECC bypass, and a large amount of ECC reaches the reactor core in the case of a large break loss-of-cooling water accident (LBLOCA) caused by DEGB. It is thus possible to limit an increase in the maximum cladding temperature of fuel rods, and to prevent the reactor core from being reheated at the late reflood phase after the DEGB-caused LBLOCA, so that the desired thermal hydraulic safety of the DVI-PLWR is secured.

    Abstract translation: 公开了一种直接容器注入型加压轻水反应堆(DVI-PLWR),其中应急芯冷却水(ECC)被直接注入反应堆容器的降液管。 在冷腿断头(CLGB)的情况下,例如双端guillo4tine断裂(DEGB),为了减少ECC旁路从降液管到冷腿的断裂面的比例,多个波纹, 具有V形横截面,以规则的间隔垂直地布置在压力容器的内表面和芯筒的外表面周围,在两个相邻的波纹之间形成有垂直的沟槽。 凹槽将ECC与在降液管中运行的流体的高速横向流相互分离,并且分离的ECC在由于重力向下流到降液管的下部之前在凹槽中以漩涡的形式停滞。 DVI-PLWR因此降低了ECC旁路的比例,并且在由DEGB引起的大的断裂损失水冷却事故(LBLOCA)的情况下,大量的ECC到达反应堆堆芯。 因此,可以限制燃料棒的最大包层温度的增加,并且在DEGB引起的LBLOCA之后防止反应堆芯在后期再掺相中再加热,使得DVI-PLWR的期望的热液压安全性 是安全的。

    Emergency core cooling duct for emergency core cooling water injection of a nuclear reactor
    4.
    发明授权
    Emergency core cooling duct for emergency core cooling water injection of a nuclear reactor 有权
    应急核心冷却水管应急核心冷却水注入核反应堆

    公开(公告)号:US08630385B2

    公开(公告)日:2014-01-14

    申请号:US12499824

    申请日:2009-07-09

    CPC classification number: G21C15/18 G21C1/086 G21C13/02 Y02E30/40

    Abstract: The present invention relates to a longitudinally divided emergency core cooling (ECC) duct in order to efficiently inject safety water to core of a pressurized light-water nuclear reactor. The ECC duct includes side supports for preventing the flow-induced vibration in the annular downcomer, and has structural stability while thermally expanding and contracting. A longitudinally divided ECC duct for emergency core cooling water injection of a nuclear reactor is provided on the periphery of a core barrel of a nuclear reactor, includes an emergency core cooling water inlet facing a direct vessel injection nozzle, and extends in a longitudinal direction of the core barrel. The longitudinally divided ECC duct is divided into a plurality of longitudinally-divided ducts in the longitudinal direction of the longitudinally divided ECC duct.

    Abstract translation: 本发明涉及一种纵向分配的应急芯冷却(ECC)管道,以便有效地将安全水注入加压轻水核反应堆的核心。 ECC管道包括用于防止环形降液管中的流动振动的侧支撑件,并且在热膨胀和收缩时具有结构稳定性。 在核反应堆的核心筒的周边设置有用于核反应堆的应急芯冷却水注入的纵向分割的ECC管道,包括面向直接容器注入喷嘴的应急芯冷却水入口,并且沿纵向方向延伸 核心桶。 纵向分割的ECC管道沿纵向分割的ECC管道的纵向被分成多个纵向分配的管道。

    PASSIVE HIGH PRESSURE SAFETY INJECTION TANK SYSTEM (HPSIT) FOR RESPONDING TO STATION BLACKOUT (SBO) AND LOSS-OF-COOLANT ACCIDENTS (LOCA)
    5.
    发明申请
    PASSIVE HIGH PRESSURE SAFETY INJECTION TANK SYSTEM (HPSIT) FOR RESPONDING TO STATION BLACKOUT (SBO) AND LOSS-OF-COOLANT ACCIDENTS (LOCA) 有权
    被动高压安全注射罐系统(HPSIT),用于响应站点黑色(SBO)和失物事件(LOCA)

    公开(公告)号:US20120263268A1

    公开(公告)日:2012-10-18

    申请号:US13189871

    申请日:2011-07-25

    CPC classification number: G21C15/18 G21D3/06 Y02E30/40

    Abstract: A high pressure safety injection tank (HPSIT) system includes one safety injection tank (HIT) which replaces a core makeup tank (CMT) and a low pressure (approximately 4.3 Mpa or below) safety injection tank (SIT) and which can shift to and operate on a high pressure (approximately 17 Mpa) operation mode, to enable injection of emergency core coolant into a reactor system both under low pressure (approximately 4.3 Mpa or below) and high pressure (approximately 17 Mpa).

    Abstract translation: 高压安全注射罐(HPSIT)系统包括一个安全注射罐(HIT),可替代核心化妆池(CMT)和低压(约4.3 Mpa或更低)安全注射罐(SIT),并可将其转移到 在高压(约17Mpa)的操作模式下操作,以便在低压(约4.3Mpa或更低))和高压(约17Mpa)下将应急芯冷却剂注入反应堆系统。

    Safety injection tank with gravity driven fluidic device
    6.
    发明授权
    Safety injection tank with gravity driven fluidic device 有权
    带重力驱动流体装置的安全注射罐

    公开(公告)号:US07920666B2

    公开(公告)日:2011-04-05

    申请号:US12128009

    申请日:2008-05-28

    CPC classification number: G21C15/18 Y02E30/32

    Abstract: A safety injection tank, used for quickly injecting emergency core cooling water (ECCW) to a reactor vessel in the case of a cold leg large break accident (CLLBA) in a pressurized water reactor (PWR), is disclosed. The safety injection tank has a gravity-driven fluidic device configured to efficiently change the ECCW injection mode from a high flow injection mode to a low flow injection mode. The gravity-driven fluidic device includes a spring placed in the upper end of the vertical pipe, and a vertically movable water tub placed on the spring so as to be movable in a vertical direction. When ECCW contained in the pressure vessel is discharged and the water level is reduced lower than the height of the tub, the tub is moved downwards such that the lower surface thereof comes into contact with the vertical pipe and closes the high flow inlet port.

    Abstract translation: 公开了一种安全注射罐,用于在压力水反应堆(PWR)中发生冷腿大断裂事故(CLLBA)的情况下将反应堆快速注入应急核心冷却水(ECCW)。 安全注射罐具有重力驱动的流体装置,其配置为有效地将ECCW注射模式从高流动注射模式改变为低流动注射模式。 重力驱动的流体装置包括放置在垂直管的上端的弹簧和放置在弹簧上的可垂直移动的水桶,以便能够在垂直方向上移动。 当包含在压力容器中的ECCW被排放并且水位降低到低于桶的高度时,桶被向下移动,使得其下表面与竖直管接触并关闭高流入口。

    EMERGENCY CORE COOLING DUCT FOR EMERGENCY CORE COOLING WATER INJECTION OF A NUCLEAR REACTOR
    7.
    发明申请
    EMERGENCY CORE COOLING DUCT FOR EMERGENCY CORE COOLING WATER INJECTION OF A NUCLEAR REACTOR 有权
    应急核心冷却水箱用于应急核心冷却水中的核反应堆

    公开(公告)号:US20100278294A1

    公开(公告)日:2010-11-04

    申请号:US12499824

    申请日:2009-07-09

    CPC classification number: G21C15/18 G21C1/086 G21C13/02 Y02E30/40

    Abstract: The present invention relates to a longitudinally divided emergency core cooling (ECC) duct in order to efficiently inject safety water to core of a pressurized light-water nuclear reactor. The ECC duct includes side supports for preventing the flow-induced vibration in the annular downcomer, and has structural stability while thermally expanding and contracting. A longitudinally divided ECC duct for emergency core cooling water injection of a nuclear reactor is provided on the periphery of a core barrel of a nuclear reactor, includes an emergency core cooling water inlet facing a direct vessel injection nozzle, and extends in a longitudinal direction of the core barrel. The longitudinally divided ECC duct is divided into a plurality of longitudinally-divided ducts in the longitudinal direction of the longitudinally divided ECC duct.

    Abstract translation: 本发明涉及一种纵向分配的应急芯冷却(ECC)管道,以便有效地将安全水注入加压轻水核反应堆的核心。 ECC管道包括用于防止环形降液管中的流动振动的侧支撑件,并且在热膨胀和收缩时具有结构稳定性。 在核反应堆的核心筒的周边设置有用于核反应堆的应急芯冷却水注入的纵向分割的ECC管道,包括面向直接容器注入喷嘴的应急芯冷却水入口,并且沿纵向方向延伸 核心桶。 纵向分割的ECC管道沿纵向分割的ECC管道的纵向被分成多个纵向分配的管道。

    Direct vessel injection (DVI) nozzle for minimum emergency core cooling (ECC) water bypass
    8.
    发明授权
    Direct vessel injection (DVI) nozzle for minimum emergency core cooling (ECC) water bypass 有权
    直接容器注入(DVI)喷嘴,用于最小应急核心冷却(ECC)水旁路

    公开(公告)号:US07809099B2

    公开(公告)日:2010-10-05

    申请号:US10985862

    申请日:2004-11-10

    CPC classification number: G21C15/18 G21C19/28 Y02E30/40

    Abstract: A direct vessel injection (DVI) nozzle for minimum emergency core coolant (ECC) bypass is disclosed. The DVI nozzle is used in a pressurized light water reactor (PLWR) having a reactor vessel with a reactor coolant system in which a coolant flows into the reactor vessel through a cold leg and passes through a reactor core prior to being discharged to the outside of the reactor vessel through a hot leg. The DVI nozzle, provided to directly inject ECC into the reactor vessel to cool the reactor core during a break in the reactor coolant system, such as a cold leg break (CLB) that may occur in the PLWR, is placed on the reactor vessel at a position horizontally offset from the central axis of the hot leg at an angle of 10° to 30° and is involved within a region defined above the central axis of the hot leg by a distance of 1.5 times the sum of diameters of the hot leg and the DVI nozzle. Thus, the DVI nozzle efficiently injects ECC, and remarkably reduces the direct ECC bypass fraction to a broken cold leg and minimizes the amount of direct ECC bypass.

    Abstract translation: 公开了用于最小应急芯冷却剂(ECC)旁路的直接容器注入(DVI)喷嘴。 DVI喷嘴用于具有反应堆容器的加压轻水反应堆(PLWR),反应堆容器具有反应堆冷却剂系统,其中冷却剂通过冷腿流入反应堆容器,并在排放到外部之前通过反应堆堆芯 反应堆容器通过热腿。 在反应堆冷却剂系统断裂期间(例如可能发生在PLWR中的冷腿断裂(CLB))的DVI喷嘴被提供以将ECC直接注入到反应器容器中以冷却反应堆堆芯在反应器容器中 以10°至30°的角度从热腿的中心轴线水平偏移的位置,并且包括在热腿的中心轴线上方的距离为热腿直径的1.5倍的区域内 和DVI喷嘴。 因此,DVI喷嘴有效地注入ECC,并且显着地将直接的ECC旁路部分减少到破碎的冷腿,并使直接ECC旁路的量最小化。

    EMERGENCY CORE COOLING SYSTEM HAVING CORE BARREL INJECTION EXTENSION DUCTS
    9.
    发明申请
    EMERGENCY CORE COOLING SYSTEM HAVING CORE BARREL INJECTION EXTENSION DUCTS 有权
    具有芯棒注射延伸管的应急芯冷却系统

    公开(公告)号:US20090232267A1

    公开(公告)日:2009-09-17

    申请号:US12123566

    申请日:2008-05-20

    Abstract: An emergency core cooling system directly injects emergency core cooling water, which is supplied from a high-pressure safety injection pump or a safety injection tank for a pressurized light water reactor, into a reactor vessel downcomer. A pipe connector is completely removed from between each direct vessel injection nozzle and each injection extension duct installed on an outer surface of the core barrel, which are opposite to each other. An emergency core cooling water intake port, through which the water is injected from each direct vessel injection nozzle, is formed on the surface of each injection extension duct facing an axis of each direct vessel injection nozzle. Thereby, a structure in which a jet of the emergency core cooling water flows into the injection extension ducts is adopted in a hydraulic connection fashion.

    Abstract translation: 应急核心冷却系统直接将应急核心冷却水从高压安全注射泵或加压轻水反应堆的安全注射罐供应到反应堆容器降液管中。 每个直接容器注入喷嘴和安装在芯筒的外表面上的彼此相对的每个注射延伸管之间的管连接器被完全移除。 在每个注射延伸管道的面对每个直接容器注射喷嘴的轴线的表面上形成有从每个直接容器注射喷嘴喷射水的应急芯冷却水进入口。 因此,以液压连接方式采用应急芯冷却水的射流流入喷射延伸管道的结构。

    WATER-SPRAY RESIDUAL HEAT REMOVAL SYSTEM FOR NUCLEAR POWER PLANT
    10.
    发明申请
    WATER-SPRAY RESIDUAL HEAT REMOVAL SYSTEM FOR NUCLEAR POWER PLANT 有权
    水力发电厂水喷雾残余热去除系统

    公开(公告)号:US20130202075A1

    公开(公告)日:2013-08-08

    申请号:US13614898

    申请日:2012-09-13

    CPC classification number: G21C15/18 G21C19/28 G21D1/02 Y02E30/40

    Abstract: A residual heat removal system for a nuclear power plant. The residual heat removal system for a nuclear power plant may include an air duct provided on an outside of a reactor containment building, a heat exchanger disposed on an inside of the air duct, a first pipe to transfer, to the heat exchanger, steam generated in a steam generator disposed on an inside of the reactor containment building, and second pipe to transfer, to the steam generator, water condensation that is cooled and condensed in the heat exchanger, wherein the heat exchanger is air-cooled using outside air flowing inside of the air duct.

    Abstract translation: 一个用于核电站的剩余散热系统。 用于核电站的剩余散热系统可以包括设置在反应堆容纳建筑物的外部的空气管道,设置在空气管道内侧的热交换器,将热交换器传送到热交换器的第一管道 在设置在反应堆容纳建筑物的内部的蒸汽发生器中,以及第二管道,用于将热交换器中冷却和冷凝的水冷凝物传递到蒸汽发生器,其中,热交换器使用在内部流动的外部空气进行空气冷却 的风道。

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