Control room for nuclear power plant
    2.
    发明授权
    Control room for nuclear power plant 有权
    核电站控制室

    公开(公告)号:US09524804B2

    公开(公告)日:2016-12-20

    申请号:US13860903

    申请日:2013-04-11

    发明人: Thomas G Graham

    IPC分类号: G21D3/00 G21D3/08 G21C1/32

    摘要: A control room for a nuclear power plant including two or more nuclear reactor units includes a central workstation providing monitoring capability for both nuclear reactor units, a first operator at the controls (OATC) workstation in front of and to one side of the central workstation providing monitoring and control capabilities for the first nuclear reactor unit, a second OATC workstation in front of and to the other side of the central workstation providing monitoring and control capabilities for the second nuclear reactor unit, and a common control workstation directly in front of the central workstation providing monitoring and control capabilities for systems serving both the first nuclear reactor unit and the second nuclear reactor unit. The central and common control workstations do not provide control capabilities for either nuclear reactor unit. The common control workstation does not include any control capabilities that must be performed by a licensed operator.

    摘要翻译: 包括两个或多个核反应堆单元的核电厂的控制室包括一个中央工作站,为两个核反应堆单元提供监控能力,一个位于中央工作站前面和一侧的控制(OATC)工作站的第一个操作员,提供 第一个核反应堆单元的监测和控制能力,第二个OATC工作站,位于中央工作站前方和另一侧,为第二个核反应堆单元提供监测和控制能力,以及一个直接位于中心前面的公共控制工作站 工作站为服务于第一核反应堆单元和第二核反应堆单元的系统提供监控和控制能力。 中央和公共控制工作站不提供任何核反应堆单元的控制能力。 公共控制工作站不包括必须由许可操作员执行的任何控制功能。

    FLUX-SHIFTING REACTIVITY CONTROL SYSTEM
    3.
    发明申请
    FLUX-SHIFTING REACTIVITY CONTROL SYSTEM 审中-公开
    变流反应控制系统

    公开(公告)号:US20160189805A1

    公开(公告)日:2016-06-30

    申请号:US14985138

    申请日:2015-12-30

    申请人: TerraPower, LLC

    摘要: A control assembly for a nuclear reactor includes a first reactivity control assembly having a first neutron modifying material, a second reactivity control assembly having a second neutron modifying material, and at least one drive mechanism coupled to the first neutron modifying material and the second neutron modifying material. The first neutron modifying material and the second neutron modifying material are selectively repositionable relative to a fuel region of the nuclear reactor. The at least one drive mechanism is configured to provide the first neutron modifying material and the second neutron modifying material in different directions through the fuel region thereby shifting a flux distribution within the fuel region away from the second neutron modifying material.

    摘要翻译: 用于核反应堆的控制组件包括具有第一中子修饰材料的第一反应性控制组件,具有第二中子修饰材料的第二反应性控制组件,以及耦合到第一中子修饰材料和第二中子修饰的至少一个驱动机构 材料。 第一中子修饰材料和第二中子改性材料相对于核反应堆的燃料区域选择性地可重新定位。 所述至少一个驱动机构构造成通过所述燃料区域在不同方向上提供所述第一中子修饰材料和所述第二中子修饰材料,从而使所述燃料区域内的通量分布偏离所述第二中子修饰材料。

    ENERGY STORAGE SYSTEM
    4.
    发明申请
    ENERGY STORAGE SYSTEM 审中-公开
    能源储存系统

    公开(公告)号:US20160109185A1

    公开(公告)日:2016-04-21

    申请号:US14867849

    申请日:2015-09-28

    IPC分类号: F28D20/00 G21C15/24

    摘要: Energy storage system regulating power output of a power generation plant that has a heat exchanger, primary circuit and secondary circuit, primary circuit directs primary fluid flow to components of a primary region and secondary circuit directs a secondary fluid flow to components of a secondary region, the heat exchanger is arranged so the secondary fluid flow is heated from the primary fluid flow. Energy storage arrangement makes a vessel for storing secondary fluid. Fluid transfer arrangement connects the vessel and is connectable to the heat exchanger of the power generation system to arrange the fluid transfer arrangement in fluid communication with the heat exchanger and the vessel. Bidirectional flow arrangement configured to control flow direction of fluid between the vessel and fluid transfer arrangement to selectively store heat energy from the heat exchanger in the vessel, and selectively transfer heat energy stored in the vessel to the heat exchanger.

    摘要翻译: 调节具有热交换器,初级回路和次级回路的发电厂的功率输出的能量存储系统,初级回路将初级流体引导到主要区域的组分和次级回路,将次级流体流引导到次级区域的组件, 热交换器被布置成使得二次流体流从初级流体流被加热。 能量储存装置形成用于储存次级流体的容器。 流体传送装置连接容器并且可连接到发电系统的热交换器以将流体传送装置布置成与热交换器和容器流体连通。 双向流装置,被配置为控制容器和流体传送装置之间的流体的流动方向,以选择性地储存来自容器中的热交换器的热能,并且选择性地将存储在容器中的热能转移到热交换器。

    DEVICE FOR HEATING A PRESSURISER
    5.
    发明申请
    DEVICE FOR HEATING A PRESSURISER 审中-公开
    用于加热压力机的装置

    公开(公告)号:US20150332797A1

    公开(公告)日:2015-11-19

    申请号:US14760918

    申请日:2014-01-15

    发明人: Jean-Pierre ROUX

    摘要: An induction heating device for a pressuriser of a pressurized water nuclear reactor, which pressuriser includes an enclosure having an inner wall made of magnetic material, the induction heating device including a heating module having a winding mounting, and a winding of conductive wire wound around the winding mounting, the winding generating a magnetic field when an alternating electric current passes therethrough; and a module mounting that engages with an attachment device configured to removably attach the heating module to the module mounting, the module mounting being configured to position the heating module outside of the inner wall of the enclosure of the pressuriser in a position that makes it possible to heat the inner wall of the pressuriser by magnetic induction when an electric current passes through the winding of the heating module.

    摘要翻译: 一种用于加压水核反应堆的加压器的感应加热装置,该加压器包括具有由磁性材料制成的内壁的外壳,该感应加热装置包括具有绕组安装的加热模块,以及围绕 绕组安装时,绕组在交流电流通过时产生磁场; 以及模块安装件,其与被配置为将所述加热模块可拆卸地附接到所述模块安装件的附接装置接合,所述模块安装件构造成将所述加热模块的外部位于所述加压器的外壳的内壁的位置处于使其成为可能的位置 当电流通过加热模块的绕组时通过磁感应加热加压器的内壁。

    CONTROL ROOM FOR NUCLEAR POWER PLANT
    7.
    发明申请
    CONTROL ROOM FOR NUCLEAR POWER PLANT 有权
    核电厂控制室

    公开(公告)号:US20140133618A1

    公开(公告)日:2014-05-15

    申请号:US13860903

    申请日:2013-04-11

    发明人: Thomas G. GRAHAM

    IPC分类号: G21D3/00

    摘要: A control room for a nuclear power plant including two or more nuclear reactor units includes a central workstation providing monitoring capability for both nuclear reactor units, a first operator at the controls (OATC) workstation in front of and to one side of the central workstation providing monitoring and control capabilities for the first nuclear reactor unit, a second OATC workstation in front of and to the other side of the central workstation providing monitoring and control capabilities for the second nuclear reactor unit, and a common control workstation directly in front of the central workstation providing monitoring and control capabilities for systems serving both the first nuclear reactor unit and the second nuclear reactor unit. The central and common control workstations do not provide control capabilities for either nuclear reactor unit. The common control workstation does not include any control capabilities that must be performed by a licensed operator.

    摘要翻译: 包括两个或多个核反应堆单元的核电厂的控制室包括一个中央工作站,为两个核反应堆单元提供监控能力,一个位于中央工作站前面和一侧的控制(OATC)工作站的第一个操作员,提供 第一个核反应堆单元的监测和控制能力,第二个OATC工作站,位于中央工作站前方和另一侧,为第二个核反应堆单元提供监测和控制能力,以及一个直接位于中心前面的公共控制工作站 工作站为服务于第一核反应堆单元和第二核反应堆单元的系统提供监控和控制能力。 中央和公共控制工作站不提供任何核反应堆单元的控制能力。 公共控制工作站不包括必须由许可操作员执行的任何控制功能。

    Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor
    9.
    发明授权
    Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor 失效
    沸水反应堆监测方法和监测程序,沸水反应堆的声阻尼方法

    公开(公告)号:US08571163B2

    公开(公告)日:2013-10-29

    申请号:US13192606

    申请日:2011-07-28

    IPC分类号: G21C17/00

    摘要: A method for monitoring and acoustic damping a boiling water reactor which includes: a reactor pressure vessel; a steam pipe for transporting steam out from a steam dome of the reactor pressure vessel; a high pressure turbine driven by the steam; a feedwater heater which heats feedwater supplied to the reactor pressure vessel using bleed steam from the high pressure turbine; a bleeding valve which adjusts a flow rate of the bleed steam; and a pressure sensor provided in a main steam line including the steam dome and the steam pipe. The method includes monitoring a fluctuating pressure in the main steam line and controlling an opening degree of the bleeding valve based on a magnitude of the fluctuating pressure.

    摘要翻译: 一种用于沸水反应器的监测和声阻尼的方法,包括:反应堆压力容器; 蒸汽管,用于将蒸汽从反应堆压力容器的蒸汽圆顶运出; 由蒸汽驱动的高压涡轮机; 给水加热器,其使用来自高压涡轮机的排出蒸汽加热供应到反应堆压力容器的给水; 调节排出蒸汽的流量的排出阀; 以及设置在包括蒸汽穹顶和蒸汽管的主蒸汽管线中的压力传感器。 该方法包括监测主蒸汽管线中的波动压力并基于波动压力的大小来控制排气阀的开度。

    Methods and devices relating to a nuclear light water reactor of the boiling water kind
    10.
    发明授权
    Methods and devices relating to a nuclear light water reactor of the boiling water kind 有权
    与沸水类型的核轻水反应堆相关的方法和装置

    公开(公告)号:US08149981B2

    公开(公告)日:2012-04-03

    申请号:US12244812

    申请日:2008-10-03

    IPC分类号: G21C19/00

    摘要: A method of determining the R-factor for a bundle of nuclear fuel rods in a nuclear light water reactor of the boiling water reactor kind. The R-factor is a factor that accounts for the weighted local power influence on a fuel rod. A local R-factor (Ri(z)) is determined for each fuel rod (i) in said bundle and for each of a plurality of levels (z) in an axial direction. The individual axial heat generation profile for a certain fuel rod (i) is taken into account when determining the local R-factors (Ri(z)) for said fuel rod (i). A processor is configured for automatically determining the R-factor. A computer program product, a method of determining the critical power for a bundle of fuel rods, a nuclear energy plant, and a method of operating a nuclear energy plant are also described.

    摘要翻译: 确定沸水反应堆类型的核轻水反应堆中一束核燃料棒的R因子的方法。 R因子是一个因素,说明加权局部力对燃料棒的影响。 对于所述束中的每个燃料棒(i)和沿轴向方向上的多个水平(z)中的每一个确定局部R因子(Ri(z))。 当确定所述燃料棒(i)的局部R因子(Ri(z))时,考虑到某个燃料棒(i)的各个轴向发热曲线。 处理器被配置为自动确定R因子。 还描述了计算机程序产品,确定一束燃料棒的关键功率的方法,核能装置以及操作核能装置的方法。