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    SMALL LOAD-FOLLOWING NUCLEAR POWER GENERATION SYSTEM USING HEAT DEFORMATION OF REFLECTOR CAUSED BY THERMAL EXPANSION PHENOMENON
    1.
    发明申请
    SMALL LOAD-FOLLOWING NUCLEAR POWER GENERATION SYSTEM USING HEAT DEFORMATION OF REFLECTOR CAUSED BY THERMAL EXPANSION PHENOMENON 审中-公开

    公开(公告)号：US20170213610A1

    公开(公告)日：2017-07-27

    申请号：US15329646

    申请日：2016-01-25

    申请人： CLEAR INC.

    发明人： Osao SUMITA ,  Isao UENO ,  Takehiko YOKOMINE

    IPC分类号： G21D3/12 ,  G21C7/10 ,  G21D3/16

    摘要： The present invention provides a small nuclear power generation system being safe and easily controlled by load following, and allowing reductions in manufacturing costs and maintenance and management costs. The small nuclear power generation system has a small nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core 4 having metallic fuel containing one or both of uranium (235, 238) and plutonium-239; a reactor vessel 1 containing the fuel assembly reactor core 4; metallic sodium loaded into the reactor vessel 1 and heated by the fuel assembly reactor core 4; and a neutron reflector 2 for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the fuel assembly reactor core 4 being maintained at or above about 1. The load following control method of the reactor allows a neutron effective multiplication factor to be controlled by coupling the neutron reflector to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector

    Reactor-turbine control for low steam pressure operation in a pressurized water reactor
    2.
    发明授权
    Reactor-turbine control for low steam pressure operation in a pressurized water reactor 失效
    反应器 - 涡轮机控制在压力水反应堆中的低蒸汽压力操作

    公开(公告)号：US4000037A

    公开(公告)日：1976-12-28

    申请号：US419746

    申请日：1973-11-28

    申请人： Michael S. Nusbaum ,  Vincent P. Buscemi ,  George J. Silvestri, Jr.

    发明人： Michael S. Nusbaum ,  Vincent P. Buscemi ,  George J. Silvestri, Jr.

    IPC分类号： G21D3/08 ,  G21C7/00 ,  G21C7/32 ,  G21D3/00 ,  G21D3/16 ,  G21C17/00

    CPC分类号： G21D3/16 ,  G21C7/00 ,  G21C7/32 ,  G21D3/00 ,  G21Y2002/201 ,  G21Y2004/302 ,  G21Y2004/40 ,  Y02E30/32 ,  Y02E30/39

    摘要： A control system for a pressurized water reactor power plant. The control system comprises temperature sensing means having flow interruption means connected thereto. The temperature sensing means monitors the temperature levels within the reactor element and sends a predetermined signal to the flow interruption means upon a predetermined change in reactor temperature. The flow interruption means is disposed within an associated steam turbine loop including a steam generator element which transforms secondary water into steam to act as motive fluid within the turbine loop. The flow interruption means initiate one or more flow interruption activities which either produce an increased temperature differential between the secondary water and the steam produced therefrom or increase the rate of flow of steam within the associated steam turbine loop. Utilization of the control system permits extensive operation of the reactor element past the end of the normal fuel cycle life. In addition, the control system provides improved reactor load follow capability.

    摘要翻译： 压水堆发电厂控制系统。 控制系统包括具有连接到其上的流动中断装置的温度检测装置。 温度检测装置监测反应堆元件内的温度水平，并且在反应器温度的预定变化时将预定信号发送到流量中断装置。 流动中断装置设置在相关联的汽轮机回路中，包括蒸汽发生器元件，该蒸汽发生器元件将二次水转化为蒸汽以在涡轮机回路内充当动力流体。 流动中断装置启动一个或多个流动中断活动，其中产生二次水和由此产生的蒸汽之间的温度差异增加，或增加相关汽轮机回路内蒸汽的流量。 控制系统的使用允许反应器元件在正常燃料循环寿命结束之后的大量操作。 此外，控制系统提供改进的反应堆负载跟随能力。

    Method for operating a pressurized water reactor during load monitoring
    3.
    发明授权
    Method for operating a pressurized water reactor during load monitoring 有权

    公开(公告)号：US09905321B2

    公开(公告)日：2018-02-27

    申请号：US14005065

    申请日：2012-03-15

    申请人： Alain Grossetete

    发明人： Alain Grossetete

    IPC分类号： G21C7/08 ,  G21D3/00 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16

    CPC分类号： G21D3/001 ,  G21C7/08 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

    摘要： The present invention relates to a method for controlling a pressurized water reactor (100) comprising the steps that involve measuring the effective power (Pe) of the nuclear reactor; acquiring a reference value for the desired power (Pc); acquiring an estimated duration (DURATION) for the increase in power in order to achieve said reference value of the target power (Pc) desired, said estimated duration (DURATION) corresponding to the time taken for the power to increase from said effective power (Pe) to said reference value for the target power (Pc); determining the reference position (Z) of at least one control rod cluster among said plurality of control rod clusters (40) in order to achieve said reference value for said target power (Pc) desired as a function of said estimated duration (DURATION), of said measured effective power (Pe) and of said reference value for said target power (Pc); monitoring the position of said at least one control rod cluster so as to position it in its reference position (Z).

    METHOD FOR OPERATING A PRESSURIZED WATER REACTOR DURING LOAD MONITORING
    4.
    发明申请
    METHOD FOR OPERATING A PRESSURIZED WATER REACTOR DURING LOAD MONITORING 有权
    负荷监测期间加压水反应器的运行方法

    公开(公告)号：US20160329116A1

    公开(公告)日：2016-11-10

    申请号：US14005065

    申请日：2012-03-15

    申请人： Alain GROSSETETE

    发明人： Alain GROSSETETE

    IPC分类号： G21D3/00 ,  G21D3/16 ,  G21D3/10 ,  G21C7/08 ,  G21C7/22

    CPC分类号： G21D3/001 ,  G21C7/08 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

    摘要： The present invention relates to a method for controlling a pressurized water reactor (100) comprising the steps that involve measuring the effective power (Pe) of the nuclear reactor; acquiring a reference value for the desired power (Pc); acquiring an estimated duration (DURATION) for the increase in power in order to achieve said reference value of the target power (Pc) desired, said estimated duration (DURATION) corresponding to the time taken for the power to increase from said effective power (Pe) to said reference value for the target power (Pc); determining the reference position (Z) of at least one control rod cluster among said plurality of control rod clusters (40) in order to achieve said reference value for said target power (Pc) desired as a function of said estimated duration (DURATION), of said measured effective power (Pe) and of said reference value for said target power (Pc); monitoring the position of said at least one control rod cluster so as to position it in its reference position (Z).

    摘要翻译： 本发明涉及一种用于控制压水反应堆（100）的方法，包括测量核反应堆的有效功率（Pe）的步骤; 获取所需功率（Pc）的参考值; 获取用于增加功率的估计持续时间（DURATION），以实现所需目标功率（Pc）的所述参考值，所述估计持续时间（DURATION）对应于从所述有效功率增加功率所花费的时间（Pe ）到目标功率（Pc）的所述参考值; 确定所述多个控制棒簇（40）中的至少一个控制棒簇的参考位置（Z），以便根据所述估计持续时间（DURATION）达到所需要的所述目标功率（Pc）的所述参考值， 的所述测量有效功率（Pe）和所述目标功率（Pc）的所述参考值; 监视所述至少一个控制棒组的位置，以将其定位在其参考位置（Z）中。

    CONTROLLING A NUCLEAR REACTION
    7.
    发明申请
    CONTROLLING A NUCLEAR REACTION 审中-公开

    公开(公告)号：US20200027603A1

    公开(公告)日：2020-01-23

    申请号：US16237027

    申请日：2018-12-31

    申请人： NuScale Power, LLC

    发明人： Allyson Callaway ,  Ben Bristol ,  Kenneth Rooks ,  Larry Linik

    IPC分类号： G21D3/02 ,  G21C7/12 ,  G21D1/00 ,  G21D3/14 ,  G21D3/16 ,  G21D5/08 ,  F22B35/00 ,  G21C7/24 ,  G21C1/02

    摘要： A nuclear power system includes a reactor vessel that includes a reactor core that includes nuclear fuel assemblies configured to generate a nuclear fission reaction; a riser positioned above the reactor core; a primary coolant flow path that extends from a bottom portion of the volume through the reactor core and through an annulus between the riser and the reactor vessel; a primary coolant that circulates through the primary coolant flow path to receive heat from the nuclear fission reaction and release the heat to generate electric power in a power generation system; and a control rod assembly system positioned in the reactor vessel and configured to position control rods in only two discrete positions.

    Method of determining and evaluating the power return capacity of a pressurized water nuclear reactor
    8.
    发明授权
    Method of determining and evaluating the power return capacity of a pressurized water nuclear reactor 失效
    确定和评估加压水核反应堆功率回收能力的方法

    公开(公告)号：US5039473A

    公开(公告)日：1991-08-13

    申请号：US333661

    申请日：1989-04-05

    申请人： Patrick Girieud

    发明人： Patrick Girieud

    IPC分类号： G21C17/00 ,  G21C7/36 ,  G21D3/12 ,  G21D3/16

    CPC分类号： G21C7/36 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

    摘要： Method for determining a evaluating the capacity of a pressurized water nuclear reactor to return to power rapidly, consisting in calculating a pick-up power by applying the general formula:Prip=Prel+.DELTA.Pin which Prip is the maximum pick-up power obtainable by acting on the control bars, Prel is the relative power delivered by the core, determined by the in-line measurement of the neutron flow emitted by the core and .DELTA.P is the additional power resulting from the potential reactivity of the assembly of control bars of the reactor when this assembly passes from the observed insertion to the minimum insertion, P being calculated from the measured position of the power regulation clusters, involving the axial power distribution measured (C1 to C6) and the previously defined exhaustion of the core.

    摘要翻译： 用于确定加压水核反应堆快速返回功率的能力的方法，其包括通过应用以下通式计算拾取功率：Prip = Prel + DELTA P，其中Prip是可由下式获得的最大拾取功率： 作用在控制杆上，Prel是由核心发射的中子流的在线测量确定的核心传递的相对功率，DELTA P是由控制棒组件的潜在反应性产生的附加功率 当该组件从观察到的插入传递到最小插入时，反应器P从功率调节簇的测量位置计算，涉及所测量的轴向功率分布（C1至C6）和先前确定的芯的耗尽。

    Process for automatic regulation of the soluble boron content of the cooling water of a pressurized water nuclear reactor
    9.
    发明授权
    Process for automatic regulation of the soluble boron content of the cooling water of a pressurized water nuclear reactor 失效
    自动调节加压水核反应堆冷却水中可溶性硼含量的方法

    公开(公告)号：US4844856A

    公开(公告)日：1989-07-04

    申请号：US589788

    申请日：1984-03-15

    申请人： Yvan Cohen ,  Pierre Deroubaix

    发明人： Yvan Cohen ,  Pierre Deroubaix

    IPC分类号： G21C7/22 ,  G21C7/08 ,  G21D3/16

    CPC分类号： G21C7/08 ,  G21D3/16 ,  G21Y2002/205 ,  G21Y2004/10 ,  G21Y2004/40 ,  G21Y2004/401 ,  Y02E30/32 ,  Y02E30/39

    摘要： A process for automatic regulation of the soluble boron content of the cooling water of a pressurized water nuclear reactor in which operating regions (2, 3) of the means of boration and of the means of dilution respectively are determined a priori, corresponding to pairs of values of two control parameters relating to the position of the reactor regulating group in the core and to the deviation of the axial power imbalance relative to the reference axial imbalance. The momentary value of the control parameters is determined continuously during the operation of the reactor, and the stopping or the triggering of the means for boration or for dilution is commanded when the operating point crosses a boundary of an operating region (2, 3).The invention applies in particular to a nuclear reactor controlled in G mode.

    摘要翻译： 一种用于自动调节加压水核反应堆的冷却水的可溶性硼含量的方法，其中分别确定了装置和稀释装置的操作区域（2,3），对应于 与反应堆调节组在芯中的位置有关的两个控制参数的值以及轴向功率不平衡相对于参考轴向不平衡的偏差。 控制参数的瞬时值在反应器的操作期间连续地确定，并且当工作点穿过操作区域（2,3）的边界时，命令停止或触发装置或稀释装置。 本发明特别适用于以G模式控制的核反应堆。