会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 1. 发明申请
    • NUCLEAR REACTOR CAVITY FLOOR PASSIVE HEAT REMOVAL SYSTEM
    • 核反应堆空间被动热除气系统
    • WO2015191453A1
    • 2015-12-17
    • PCT/US2015/034678
    • 2015-06-08
    • BABCOCK & WILCOX MPOWER, INC.
    • EDWARDS, Tyler A.NEELEY, Gary W.INMAN, James B.
    • G21C9/016
    • G21C9/00G21C9/016Y02E30/40
    • A nuclear reactor includes a reactor core disposed in a reactor pressure vessel. A radiological containment contains the nuclear reactor and includes a concrete floor located underneath the nuclear reactor. An ex vessel corium retention system includes flow channels embedded in the concrete floor located underneath the nuclear reactor, an inlet in fluid communication with first ends of the flow channels, and an outlet in fluid communication with second ends of the flow channels. In some embodiments the inlet is in fluid communication with the interior of the radiological containment at a first elevation and the outlet is in fluid communication with the interior of the radiological containment at a second elevation higher than the first elevation. The radiological containment may include a reactor cavity containing a lower portion of the pressure vessel, wherein the concrete floor located underneath the nuclear reactor is the reactor cavity floor.
    • 核反应堆包括设置在反应堆压力容器中的反应堆芯。 放射性容纳物包含核反应堆,并包括位于核反应堆下方的混凝土地板。 一种前血管ium ium保持系统包括嵌入在核反应堆下方的混凝土地板中的流动通道,与流动通道的第一端流体连通的入口以及与流动通道的第二端流体连通的出口。 在一些实施例中,入口在第一高度处与放射性容纳物的内部流体连通,并且出口在高于第一高度的第二高度处与放射性容纳物的内部流体连通。 放射性容纳物可以包括含有压力容器下部的反应器空腔,其中位于核反应堆下方的混凝土地板是反应堆空腔底板。
    • 2. 发明申请
    • RISER TRANSITION ELEMENT FOR COMPACT NUCLEAR REACTOR
    • 紧凑型核反应堆的上升过渡元件
    • WO2013162898A3
    • 2015-06-18
    • PCT/US2013036094
    • 2013-04-11
    • BABCOCK & WILCOX MPOWER INC
    • SHARGOTS SCOTT J
    • G21C15/14
    • G21C7/12E02D29/12G21C1/32G21C5/06G21C5/10G21C7/08G21C13/024G21C19/10G21C19/19G21C19/20G21C19/205Y02E30/40
    • A nuclear reactor core is disposed in a pressure vessel along with upper internals disposed in the pressure vessel above the reactor core. The upper internals include internal control rod drive mechanisms (CRDMs) mounted on a suspended support assembly. A hollow cylindrical central riser is disposed in the pressure vessel above the nuclear reactor core. A hollow cylindrical section is disposed in the pressure vessel below the hollow cylindrical central riser and surrounding the nuclear reactor core. A riser transition element connects with the hollow cylindrical central riser and the hollow cylindrical section to form a continuous hollow cylindrical flow separator. The suspended support assembly of the upper internals is suspended from the riser transition element. The pressure vessel may comprise upper and lower vessel sections connected by a mid-flange, with the riser transition element welded to the mid-flange by gussets extending outward and upward from the riser transition element to the mid-flange.
    • 核反应堆核心与设置在反应堆堆芯上方的压力容器中的上部内件一起设置在压力容器中。 上部内部件包括安装在悬挂的支撑组件上的内部控制杆驱动机构(CRDM)。 中空的圆柱形中央提升管设置在核反应堆核心上方的压力容器中。 中空圆柱形部分设置在中空圆柱形中央提升管下方的压力容器中并围绕核反应堆核心。 提升过渡元件与中空圆柱形中心提升管和中空圆柱形部分连接以形成连续的中空圆柱形流动分离器。 上部内件的悬挂的支撑组件从提升板过渡元件悬挂。 压力容器可以包括通过中间凸缘连接的上部和下部容器部分,其中提升管过渡元件通过从提升管过渡元件向外和向上延伸到中间凸缘的角撑板焊接到中间凸缘。
    • 3. 发明申请
    • CONTROL ROOM FOR NUCLEAR POWER PLANT
    • 核电厂控制室
    • WO2014021952A3
    • 2014-07-17
    • PCT/US2013036271
    • 2013-04-12
    • BABCOCK & WILCOX MPOWER INC
    • GRAHAM THOMAS G
    • G21C17/00G21D3/00
    • G21C17/00G21D3/00G21D3/008Y02E30/40
    • A reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.
    • 反应堆控制接口包括主屏幕视频显示单元(VDU),其显示表示核电站的功能部件的块,并连接提供核电站的当前散热路径的块连接的箭头。 连接箭头的方向表示沿着当前散热路径的热流方向。 如果工厂当前的热流路径发生变化,则连接箭头会相应更新。 额外的VDU包括:模拟VDU,显示工厂组件的模拟; 显示可由工厂执行的存储过程的过程VDU; 多趋势VDU趋向各种工厂数据; 并且报警VDU分别显示按时间和优先级排列的并排报警注册表。 如果VDU发生故障,显示屏将被移动以释放一个VDU来显示发生故障的VDU的显示,并且一个显示器将转移到另一个VDU。
    • 6. 发明申请
    • SUSPENDED UPPER INTERNALS WITH TIE ROD COUPLINGS FOR COMPACT NUCLEAR REACTOR
    • 用于紧凑型核反应堆的TIE ROD联轴器的悬挂式上部内部
    • WO2013165669A1
    • 2013-11-07
    • PCT/US2013/036126
    • 2013-04-11
    • BABCOCK & WILCOX MPOWER, INC.
    • SHARGOTS, Scott, J.
    • G21C1/00
    • G21C7/117G21C1/086G21C1/322G21C5/02G21C5/10G21C7/12Y02E30/39
    • A suspended basket includes a plurality of plates, tie rods, and adjustable length threaded tie rod couplings connecting threaded ends of the tie rods with threaded features of the plates. Control rod drive mechanisms (CRDMs) with CRDM motors are mounted in the suspended basket, which is suspended in a pressure vessel above a nuclear reactor core to control insertion of control rods into the reactor core. In one embodiment each adjustable length threaded tie rod coupling is a turnbuckle coupling that includes a sleeve threaded onto the threaded end of the tie rod and onto the threaded feature of the plate, and the sleeve is rotatable to adjust the position of the tie rod respective to the plate. Guide frames may be mounted in the suspended basket between the CRDMs and the nuclear reactor core to guide portions of the control rods withdrawn from the nuclear reactor core.
    • 悬挂的篮子包括多个板,拉杆和可调节长度的螺纹拉杆联轴器,其将带有螺纹特征的拉杆的螺纹端连接在一起。 具有CRDM电动机的控制杆驱动机构(CRDM)安装在悬挂篮中,悬挂篮悬挂在核反应堆堆芯上方的压力容器中,以控制将控制棒插入反应堆堆芯。 在一个实施例中,每个可调节长度的螺纹连杆联轴器是螺丝扣联接器,其包括螺纹连接到拉杆的螺纹端部并且到达板的螺纹特征的套筒,并且套筒可旋转以调节拉杆的位置 到盘子 引导框架可以安装在CRDM和核反应堆堆芯之间的悬挂篮中,以引导从核反应堆堆芯取出的控制棒的部分。
    • 7. 发明申请
    • CRDM INTERNAL HYDRAULIC CONNECTOR
    • CRDM内部液压连接器
    • WO2013165667A2
    • 2013-11-07
    • PCT/US2013/036072
    • 2013-04-11
    • BABCOCK & WILCOX MPOWER, INC.
    • SHARGOTS, Scott, J
    • G21C7/16G21C7/12G21C7/14H05K13/00
    • G21C7/16G21C7/12G21C13/02Y02E30/39Y10T29/49826
    • In a nuclear reactor, an internal control rod drive mechanism (CRDM) includes a motor and a hydraulically driven element connected by at least one hydraulic line with at least one hydraulic connector disposed on a mounting plate of the internal CRDM. A support element mounted in the nuclear reactor includes at least one hydraulic connector. The internal CRDM is supported on the support element by its mounting plate with each hydraulic connector of the internal CRDM mated with a corresponding hydraulic connector of the support element. The hydraulically driven element may be a piston controlling SCRAM, driven by coolant water, and the coolant water pressure in the at least one hydraulic line is higher than the coolant water pressure in the nuclear reactor. The mating of each hydraulic connector of the internal CRDM with a corresponding hydraulic connector of the support element may be a leaky mating that leaks coolant water into the pressure vessel.
    • 在核反应堆中,内部控制杆驱动机构(CRDM)包括电动机和液压驱动元件,所述液压驱动元件通过至少一个液压管路连接,至少一个液压连接器设置在内部CRDM的安装板上。 安装在核反应堆中的支撑元件包括至少一个液压连接器。 内部CRDM通过其安装板支撑在支撑元件上,内部CRDM的每个液压连接器与支撑元件的相应液压连接器配合。 液压驱动元件可以是控制SCRAM的活塞,由冷却水驱动,并且至少一个液压管路中的冷却水压力高于核反应堆中的冷却水压力。 内部CRDM的每个液压连接器与支撑元件的相应的液压连接器的配合可以是将冷却水泄漏到压力容器中的泄漏配合。
    • 8. 发明申请
    • RISER TRANSITION ELEMENT FOR COMPACT NUCLEAR REACTOR
    • 紧凑型核反应堆的上升过渡元件
    • WO2013162898A2
    • 2013-10-31
    • PCT/US2013/036094
    • 2013-04-11
    • BABCOCK & WILCOX MPOWER, INC.
    • SHARGOTS, Scott, J.
    • G21C7/12G21C19/20
    • G21C7/12E02D29/12G21C1/32G21C5/06G21C5/10G21C7/08G21C13/024G21C19/10G21C19/19G21C19/20G21C19/205Y02E30/40
    • A nuclear reactor core is disposed in a pressure vessel along with upper internals disposed in the pressure vessel above the reactor core. The upper internals include internal control rod drive mechanisms (CRDMs) mounted on a suspended support assembly. A hollow cylindrical central riser is disposed in the pressure vessel above the nuclear reactor core. A hollow cylindrical section is disposed in the pressure vessel below the hollow cylindrical central riser and surrounding the nuclear reactor core. A riser transition element connects with the hollow cylindrical central riser and the hollow cylindrical section to form a continuous hollow cylindrical flow separator. The suspended support assembly of the upper internals is suspended from the riser transition element. The pressure vessel may comprise upper and lower vessel sections connected by a mid-flange, with the riser transition element welded to the mid-flange by gussets extending outward and upward from the riser transition element to the mid-flange.
    • 核反应堆核心与设置在反应堆堆芯上方的压力容器中的上部内件一起设置在压力容器中。 上部内部件包括安装在悬挂支撑组件上的内部控制杆驱动机构(CRDM)。 中空圆柱形中央提升管设置在核反应堆核心上方的压力容器中。 中空圆柱形部分设置在中空圆柱形中央提升管下方的压力容器中并围绕核反应堆核心。 提升过渡元件与中空圆柱形中央提升管和中空圆柱形部分连接,以形成连续的中空圆柱形流动分离器。 上部内件的悬挂的支撑组件从立管过渡元件悬挂。 压力容器可以包括通过中间凸缘连接的上部和下部容器部分,其中提升过渡元件通过从提升管过渡元件向外和向上延伸到中间凸缘的角撑板焊接到中间凸缘。
    • 10. 发明申请
    • INTEGRAL VESSEL ISOLATION VALVE
    • 集成式隔离阀
    • WO2013158762A1
    • 2013-10-24
    • PCT/US2013/036973
    • 2013-04-17
    • BABCOCK & WILCOX MPOWER, INC.
    • MALLOY, John, D. IIIALES, MatthewEDWARDS, Michael, J.WATSON, Ronald, CWHITTEN, Andrew, C.
    • F16K15/00F16K15/10
    • G21C13/02G21C9/00G21C13/0285G21C15/24Y02E30/40
    • A nuclear reactor comprises a nuclear reactor core disposed in a pressure vessel. An isolation valve protects a penetration through the pressure vessel. The isolation valve comprises: a mounting flange connecting with a mating flange of the pressure vessel; a valve seat formed into the mounting flange; and a valve member movable between an open position and a closed position sealing against the valve seat. The valve member is disposed inside the mounting flange or inside the mating flange of the pressure vessel. A biasing member operatively connects to the valve member to bias the valve member towards the open position. The bias keeps the valve member in the open position except when a differential fluid pressure across the isolation valve and directed outward from the pressure vessel exceeds a threshold pressure.
    • 核反应堆包括设置在压力容器中的核反应堆堆芯。 隔离阀保护穿过压力容器的穿透。 隔离阀包括:与压力容器的配合凸缘连接的安装凸缘; 形成在安装凸缘中的阀座; 以及阀构件,其能够在打开位置和关闭位置之间移动,从而与阀座密封。 阀构件设置在安装凸缘的内部或压力容器的配合凸缘的内部。 偏置构件可操作地连接到阀构件以将阀构件偏压到打开位置。 偏压保持阀构件处于打开位置,除了跨过隔离阀并且从压力容器向外指向的差动流体压力超过阈值压力时。