公开(公告)号：WO2015191453A1

公开(公告)日：2015-12-17

申请号：PCT/US2015/034678

申请日：2015-06-08

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： EDWARDS, Tyler A. ,  NEELEY, Gary W. ,  INMAN, James B.

IPC: G21C9/016

CPC classification number: G21C9/00 ,  G21C9/016 ,  Y02E30/40

Abstract: 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.

Abstract translation: 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。

公开(公告)号：WO2013162898A3

公开(公告)日：2015-06-18

申请号：PCT/US2013036094

申请日：2013-04-11

Applicant: BABCOCK & WILCOX MPOWER INC

Inventor： SHARGOTS SCOTT J

IPC: G21C15/14

CPC classification number: G21C7/12 ,  E02D29/12 ,  G21C1/32 ,  G21C5/06 ,  G21C5/10 ,  G21C7/08 ,  G21C13/024 ,  G21C19/10 ,  G21C19/19 ,  G21C19/20 ,  G21C19/205 ,  Y02E30/40

Abstract: 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.

Abstract translation: 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。

公开(公告)号：WO2014021952A3

公开(公告)日：2014-07-17

申请号：PCT/US2013036271

申请日：2013-04-12

Applicant: BABCOCK & WILCOX MPOWER INC

Inventor： GRAHAM THOMAS G

IPC: G21C17/00 ,  G21D3/00

CPC classification number: G21C17/00 ,  G21D3/00 ,  G21D3/008 ,  Y02E30/40

Abstract: 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.

Abstract translation: 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。

公开(公告)号：WO2013172891A3

公开(公告)日：2013-11-21

申请号：PCT/US2013/026450

申请日：2013-02-15

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： RUSSELL, William, E. ,  BARGER, Earl, B ,  RIDGEWAY, Roger, D ,  LEE, Jeffrey, T ,  AUSTIN, Jeffrey, W ,  MINOR, David, M

IPC: G21C3/10

Abstract: A pedestal plug is sized to fit into a cladding of a nuclear fuel rod. A lower end plug is sized and shaped to plug the lower end of the nuclear fuel rod. One of the pedestal plug and the lower end plug includes a protrusion and the other of the pedestal plug and the lower end plug includes a hollow region into which the protrusion fits. In one embodiment the pedestal plug is a hollow cylindrical pedestal plug and the protrusion is disposed on the lower end plug. The protrusion disposed on the lower end plug suitably press fits into the hollow cylindrical pedestal plug. In a method of assembling a fuel rod of a nuclear reactor, the pedestal plug and the lower end plug are press fit together, and after the press fitting the lower end plug is welded to a cladding of the fuel rod with the pedestal plug disposed inside the cladding.

公开(公告)号：WO2013172889A1

公开(公告)日：2013-11-21

申请号：PCT/US2013/026242

申请日：2013-02-15

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： LEE, Jeffrey, T. ,  PABIS, George, S. ,  RIDGEWAY, Roger, D.

IPC: G21C5/06

CPC classification number: G21C3/33 ,  G21C3/3206 ,  G21C3/3305 ,  Y02E30/40

Abstract: A fuel assembly including a plurality of fuel rods arranged mutually in parallel wherein the fuel rods include a fissile material, a plurality of guide tubes arranged in parallel with and interspersed amongst the fuel rods, an upper end fitting connected with upper ends of the guide tubes, and a lower end fitting connected with lower ends of the guide tubes. At least one of the upper end fitting and the lower end fitting includes a grid formed by interlocking metal strips secured together at intersections between the metal strips.

Abstract translation: 一种燃料组件，包括相互并联布置的多个燃料棒，其中所述燃料棒包括易裂变材料，多个导管与所述燃料棒平行布置并散布在所述燃料棒中;上端配件，其与所述导管的上端连接 以及与引导管的下端连接的下端配件。 上端配件和下端配件中的至少一个包括通过互锁的金属条形成的格栅，金属条固定在金属条之间的交叉处。

公开(公告)号：WO2013165669A1

公开(公告)日：2013-11-07

申请号：PCT/US2013/036126

申请日：2013-04-11

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： SHARGOTS, Scott, J.

IPC: G21C1/00

CPC classification number: G21C7/117 ,  G21C1/086 ,  G21C1/322 ,  G21C5/02 ,  G21C5/10 ,  G21C7/12 ,  Y02E30/39

Abstract: 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.

Abstract translation: 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。

公开(公告)号：WO2013165667A2

公开(公告)日：2013-11-07

申请号：PCT/US2013/036072

申请日：2013-04-11

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： SHARGOTS, Scott, J

IPC: G21C7/16 ,  G21C7/12 ,  G21C7/14 ,  H05K13/00

CPC classification number: G21C7/16 ,  G21C7/12 ,  G21C13/02 ,  Y02E30/39 ,  Y10T29/49826

Abstract: 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.

Abstract translation: 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。

公开(公告)号：WO2013162898A2

公开(公告)日：2013-10-31

申请号：PCT/US2013/036094

申请日：2013-04-11

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： SHARGOTS, Scott, J.

IPC: G21C7/12 ,  G21C19/20

CPC classification number: G21C7/12 ,  E02D29/12 ,  G21C1/32 ,  G21C5/06 ,  G21C5/10 ,  G21C7/08 ,  G21C13/024 ,  G21C19/10 ,  G21C19/19 ,  G21C19/20 ,  G21C19/205 ,  Y02E30/40

Abstract: 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.

Abstract translation: 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。

公开(公告)号：WO2013162668A2

公开(公告)日：2013-10-31

申请号：PCT/US2013/025048

申请日：2013-02-07

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： DOAN, Andrew, W ,  WALTON, Lewis, A ,  PABIS, George, S

IPC: G21C3/352

CPC classification number: G21C3/352 ,  G21C1/32 ,  G21C3/3563 ,  Y02E30/40

Abstract: A spacer grid includes intersecting straps defining cells with springs and dimples arranged to hold fuel rods passing through the cells. The springs are dual cantilevered springs with a bridge section between the distal end of the spring and the base. The distal portion of the spring is less stiff than the bridge section. The bridge section creates a bump which acts as a stop or travel limiter to prevent loss of grip force due to excessive spring deflection.

Abstract translation: 间隔网格包括限定具有弹簧的细胞的相交带，并且布置成保持通过细胞的燃料棒的凹坑。 弹簧是双悬臂弹簧，弹簧的远端和底座之间具有桥接部分。 弹簧的远端部分比桥接部分刚性差。 桥接部分产生一个起作用的停止或行程限制器的凸起，以防止由于过大的弹簧挠曲而造成的抓地力的损失。

公开(公告)号：WO2013158762A1

公开(公告)日：2013-10-24

申请号：PCT/US2013/036973

申请日：2013-04-17

Applicant: BABCOCK & WILCOX MPOWER, INC.

Inventor： MALLOY, John, D. III ,  ALES, Matthew ,  EDWARDS, Michael, J. ,  WATSON, Ronald, C ,  WHITTEN, Andrew, C.

IPC: F16K15/00 ,  F16K15/10

CPC classification number: G21C13/02 ,  G21C9/00 ,  G21C13/0285 ,  G21C15/24 ,  Y02E30/40

Abstract: 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.

Abstract translation: 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。