INSTRUMENTATION AND CONTROL PENETRATION FLANGE FOR PRESSURIZED WATER REACTOR
    2.
    发明申请
    INSTRUMENTATION AND CONTROL PENETRATION FLANGE FOR PRESSURIZED WATER REACTOR 有权
    用于加压水反应器的仪器和控制渗透法兰

    公开(公告)号:US20130287157A1

    公开(公告)日:2013-10-31

    申请号:US13457683

    申请日:2012-04-27

    IPC分类号: G21C13/00

    摘要: A nuclear reactor having a penetration seal ring interposed between the reactor vessel flange and a mating flange on the reactor vessel head. Radial ports through the flange provide passage into the interior of the reactor vessel for utility conduits that can be used to convey signal cables, power cables or hydraulic lines to the components within the interior of the pressure vessel. A double o-ring seal is provided on both sides of the penetration flange and partial J-welds on the inside diameter of the flange between the flange and the utility conduits secure the pressure boundary.

    摘要翻译: 一种核反应堆,其具有插入在反应堆容器凸缘和反应堆容器头部的配合凸缘之间的穿透密封环。 通过凸缘的径向通道提供通向反应堆容器的内部,用于可用于将信号电缆,电力电缆或液压管线传送到压力容器内部的部件的公用管道。 在穿透法兰的两侧设有双O型圈密封件,法兰和公用管道之间法兰内径上的部分J型焊缝固定压力边界。

    Nuclear reactor internal hydraulic control rod drive mechanism assembly
    3.
    发明授权
    Nuclear reactor internal hydraulic control rod drive mechanism assembly 有权
    核反应堆内部液压控制杆驱动机构总成

    公开(公告)号:US08953732B2

    公开(公告)日:2015-02-10

    申请号:US13314506

    申请日:2011-12-08

    IPC分类号: G21C7/06 G21C7/16 H02K33/00

    CPC分类号: G21C7/16 H02K33/00 Y02E30/39

    摘要: A control rod drive system for a nuclear reactor that employs hydraulic cylinders to operate a conventional plunger/gripper drive system to incrementally move control rods into and out of the core of a reactor. The pressure differential for driving hydraulic pistons within the cylinders is obtained from the difference in pressure between the outside and inside of the core barrel of the reactor and control of the pistons is obtained from external solenoids attached to the reactor control system. The external solenoids regulate a charging pump feed to Poppet valves that control the hydraulic feed to the cylinders. A hydraulic piston/cylinder drive is also provided for the shutdown rods which operate in either an all in or out of the core condition.

    摘要翻译: 一种用于核反应堆的控制杆驱动系统,其使用液压缸来操作常规的柱塞/夹具驱动系统,以将控制棒逐渐地移动到反应器的芯中并将其移出。 用于驱动气缸内的液压活塞的压力差是从反应堆的芯筒的外部和内部之间的压力差获得的,而活塞的控制由连接到反应器控制系统的外部螺线管获得。 外部螺线管调节充气泵进给到提升阀,控制液压进给气缸。 还提供了用于关闭杆的液压活塞/气缸驱动器,其操作在内部或外部的核心状态。

    SMALL MODULAR REACTOR SAFETY SYSTEMS
    4.
    发明申请
    SMALL MODULAR REACTOR SAFETY SYSTEMS 有权
    小型反应堆安全系统

    公开(公告)号:US20130336441A1

    公开(公告)日:2013-12-19

    申请号:US13495083

    申请日:2012-06-13

    IPC分类号: G21C9/00

    摘要: An integral pressurized water reactor that combines all of the components typically associated with a nuclear steam supply system, such as the steam generator, reactor coolant pumps, pressurizer and the reactor, into a single reactor pressure vessel. The reactor pressure vessel is itself enclosed in a containment pressure vessel that also houses a number of safety systems, such as the core make-up tanks, the primary side of residual heat removal heat exchangers, an automatic depressurization system and a recirculation system that enables continuous core cooling through natural circulation over an extended period of time. Actuation of the passive systems is done by single actuation of valves, powered from redundant batteries.

    摘要翻译: 将通常与诸如蒸汽发生器,反应堆冷却剂泵,加压器和反应器的核蒸汽供应系统相关联的所有部件组合成单个反应堆压力容器的整体式压水反应堆。 反应堆压力容器本身封闭在容纳压力容器中,该容器还容纳许多安全系统,例如核心化妆池,剩余除热热交换器的初级侧,自动减压系统和再循环系统,其使能 连续的核心冷却通过自然循环延长的时间。 被动系统的启动是通过单个致动的阀门,由冗余电池供电。

    Head assembly
    5.
    发明授权
    Head assembly 有权
    头组件

    公开(公告)号:US07158605B2

    公开(公告)日:2007-01-02

    申请号:US10670540

    申请日:2003-09-24

    IPC分类号: G21C19/00

    摘要: A head assembly for a reactor pressure vessel includes a removable closure head, an array of control rod drive mechanisms, a seismic support platform, a missile shield assembly and a cooling system for drawing atmospheric air across electromagnetic coil stack assemblies. The cooling system includes: a lower shroud surrounding the coil stack assemblies with an end open to the atmosphere around the CRDMs; a plurality of extending internal ducts disposed within the array of CRDMs upwardly to an upper plenum disposed above the seismic support platform and a plurality of fan assemblies disposed on the upper plenum. The missile shield is disposed within the upper plenum. The cooling system effectively cools the coil stack assemblies during fuel cycles and does not hinder access to the CRDMs during an outage. The head assembly has lift legs for transporting either the entire head assembly as an integral unit or the structure above the seismic support platform a subassembly.

    摘要翻译: 用于反应堆压力容器的头部组件包括可移除的封闭头,控制杆驱动机构的阵列,地震支撑平台,导弹屏蔽组件和用于在大气中横跨电磁线圈堆叠组件的冷却系统。 冷却系统包括:围绕线圈堆叠组件的下护罩,其端部围绕CRDM周围的大气敞开; 设置在所述CRDM阵列内的多个延伸的内部管道,设置在所述地震支撑平台上方的上部集气室和设置在所述上​​部气室上的多个风扇组件。 导弹防护罩设置在上部通风室内。 冷却系统在燃料循环期间有效地冷却线圈堆叠组件,并且不会妨碍在停电期间进入CRDM。 头部组件具有用于将整个头部组件作为整体单元或在地震支撑平台上方的结构传送到子组件的提升腿。

    Method of sealing a reactor pressure vessel
    6.
    发明授权
    Method of sealing a reactor pressure vessel 有权
    密封反应堆压力容器的方法

    公开(公告)号:US06301319B1

    公开(公告)日:2001-10-09

    申请号:US09407571

    申请日:1999-09-28

    IPC分类号: G21C13028

    摘要: A method of temporarily sealing a reactor pressure vessel during an outage permits the water level in the vessel to be drawn down to a level which enables the interior surfaces of associated structures and equipment in the primary coolant loop to be inspected while dry when the vessel is submerged in a pool of water. A reactor pressure vessel internals lifting rig is used to position a temporary reactor pressure vessel head having an elliptical shaped dome with a circumferential flange retaining a pair of spaced apart, circumferential seal rings onto a reactor pressure vessel circumferential flange without marking or damaging the reactor pressure vessel flange. Advantageously, the weight of the temporary head (together with the static head of water, which must be supported by the elliptical design of the dome) is sufficient to cause the seal rings to seal against the reactor pressure vessel flange without the need for studs or other mechanical fasteners or the need to pump out leakage from the pool of water above the reactor pressure vessel. The flanges and the rings define a space which is tested for leak-tightness.

    摘要翻译: 在停电期间临时密封反应堆压力容器的方法允许将容器中的水位向下拉到一定水平,使得当容器处于干燥状态时能够使主冷却剂回路中的相关结构和设备的内表面被干燥 淹没在一池水中。 使用反应堆压力容器内部升降装置来定位具有椭圆形圆顶的临时反应堆压力容器头部,其周向凸缘将一对间隔开的圆周密封环保持在反应堆压力容器圆周凸缘上,而不会标记或损坏反应器压力 船舶法兰 有利的是,临时头部的重量(与静止的水头必须由圆顶的椭圆形设计支撑)足以使得密封环密封反应堆压力容器法兰,而不需要螺柱或 其他机械紧固件或需要从反应堆压力容器上方的水池排出泄漏物。 法兰和环限定了一个空间,以便进行密封性测试。

    METHOD OF REFUELING A NUCLEAR REACTOR
    7.
    发明申请
    METHOD OF REFUELING A NUCLEAR REACTOR 有权
    修复核反应堆的方法

    公开(公告)号:US20130294565A1

    公开(公告)日:2013-11-07

    申请号:US13461821

    申请日:2012-05-02

    IPC分类号: G21C19/20

    摘要: A method of refueling a nuclear reactor that includes the steps of removing the reactor vessel head and upper internals to a storage location and installing a cylindrical tank having open upper and lower ends, on the reactor vessel flange. The cylindrical tank is sealed to the reactor vessel and a penetration on the side of the cylindrical tank is sealed to a refueling canal that is connected to a spent fuel pool. The level of reactor coolant within the reactor vessel is then raised to at least partially fill the cylindrical tank to a level equal to that of the spent fuel pool. The refueling canal is then opened and a refueling machine supported on the reactor vessel is employed to transfer fuel assemblies between the core and the spent fuel pool.

    摘要翻译: 一种对核反应堆进行加油的方法,包括以下步骤:将反应器容器头部和上部内部件移至存储位置,并在反应器容器凸缘上安装具有敞开的上端和下端的圆柱形罐。 圆筒形容器被密封到反应堆容器,并且在圆柱形容器侧面上的穿透被密封到连接到乏燃料池的加油渠。 然后将反应堆容器内的反应堆冷却剂的水平升高至至少部分地将圆筒形容器填充到与废燃料池相当的水平。 然后打开加油渠,并且使用负载在反应堆容器上的加油机来在核心和乏燃料池之间转运燃料组件。

    Method of retrofitting a reactor pressure vessel head assembly
    8.
    发明授权
    Method of retrofitting a reactor pressure vessel head assembly 有权
    改造反应堆压力容器头组件的方法

    公开(公告)号:US06639960B2

    公开(公告)日:2003-10-28

    申请号:US09972728

    申请日:2001-10-05

    IPC分类号: G21C1900

    摘要: A head assembly of a reactor pressure vessel in an ice condenser plant is retrofitted to permit the assembly to be removed during a later refueling operation in reduced time and with reduced exposure to radiation by operating personnel. The portions of the ductwork ventilation system that originally provided cooling air to CRDMs are removed below the seismic support platform. The original CRDM cooling shroud that surrounds the lower portion of the CRDM assemblies is extended to the seismic support platform. A plenum is mounted on the seismic support platform and in air flow communication with interior portion of the extended CRDM cooling shroud. The plenum fits under the missile shield. Spool pieces are connected between the plenum and the portion of the ductwork adjacent to the seismic support platform. Later, during refueling operations, the RPV head assembly can be disconnected from and reconnected to the ductwork of the ventilation system without the need for scaffolding around the RPV head assembly and with reduced exposure to radiation by operating personnel.

    摘要翻译: 在冰冷凝器设备中的反应堆压力容器的头部组件被改进以允许在稍后的加油操作期间在减少的时间内移除组件并且由操作人员减少暴露于辐射。 原来为CRDM提供冷却空气的管道系统通风系统的部分在地震支撑平台下方被移除。 围绕CRDM组件下部的原始CRDM冷却护罩延伸到地震支撑平台。 一个集气室安装在地震支撑平台上,与扩展的CRDM冷却导流罩的内部部分进行气流连通。 这个集会座位于导弹盾下。 阀芯片连接在气室和与地震支撑平台相邻的管道系统的部分之间。 之后,在加油操作期间,RPV头部组件可以与通风系统的管道系统断开连接,而不需要在RPV头部组件周围的脚手架,并且由操作人员减少暴露于辐射。

    Pressurizer surge-line separator for integral pressurized water reactors
    9.
    发明授权
    Pressurizer surge-line separator for integral pressurized water reactors 有权
    用于整体压水反应堆的加压器浪涌管分离器

    公开(公告)号:US09478317B2

    公开(公告)日:2016-10-25

    申请号:US13476191

    申请日:2012-05-21

    IPC分类号: G21C15/00 G21C1/09 G21C1/32

    摘要: An integral pressurized light water reactor having most of the components of a primary side of a pressurized water reactor nuclear steam supply system housed in a single pressure vessel with a pressurizer separated from the remaining reactor system by a surge separator having multiple layers of separated steel plates with a number of concentric baffles extending therebetween. A circuitous flow path is provided through and between the plates and concentric baffles and a relatively stagnant pool of coolant is maintained within an innermost zone between the plates to provide thermal isolation.

    摘要翻译: 一体式加压轻水反应器,其具有容纳在具有加压器的单个压力容器中的加压水反应堆核蒸汽供应系统的初级侧的大部分组分,其具有通过具有多层分离钢板的浪涌隔离器与剩余反应器系统分离 具有在其间延伸的多个同心挡板。 提供通过板和同心挡板之间的迂回流动路径,并且相对滞留的冷却剂池被保持在板之间的最内区域中以提供热隔离。

    PRESSURIZED WATER REACTOR COMPACT STEAM GENERATOR
    10.
    发明申请
    PRESSURIZED WATER REACTOR COMPACT STEAM GENERATOR 有权
    压缩水反应堆紧凑型蒸汽发生器

    公开(公告)号:US20130336442A1

    公开(公告)日:2013-12-19

    申请号:US13495050

    申请日:2012-06-13

    IPC分类号: G21C15/00

    摘要: A steam generator system for a pressurized water reactor which employs an external to containment steam drum and recirculation loop piping. The steam generator system changes the arrangement of a typical pressurized water reactor recirculation steam generator by relocating the functions of steam separation and feedwater preheating outside of the reactor coolant system. The steam generator system and thermal hydraulic conditions are selected in order to minimize the size of the steam generator heat exchanger component volume inside of the containment. The external steam drum component can be isolated in accident conditions when desired and is used as a source of secondary fluid inventory for improved decay heat removal capability and tolerance for loss of feedwater events. Thus, the steam generator component volume inside of the containment is reduced and the amount of maintenance required for the reactor coolant system components are similarly reduced.

    摘要翻译: 一种用于压水反应堆的蒸汽发生器系统,其采用外部容纳蒸汽鼓和再循环回路管道。 蒸汽发生器系统通过将反应堆冷却剂系统外部的蒸汽分离和给水预热的功能重新定位来改变典型的加压水反应堆再循环蒸汽发生器的布置。 选择蒸汽发生器系统和热液压条件以便使容纳内部的蒸汽发生器热交换器部件容积的尺寸最小化。 当需要时,外部蒸汽鼓组件可以在事故条件下隔离,并用作次要液体清单的来源,以提高脱水能力和减少给水事件损失的容限。 因此,容纳内部的蒸汽发生器部件容积减少,并且反应堆冷却剂系统部件所需的维护量相似地减少。