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    Out-of-core nuclear instrumentation device
    61.
    发明授权
    Out-of-core nuclear instrumentation device 有权

    公开(公告)号：US10650932B2

    公开(公告)日：2020-05-12

    申请号：US15541724

    申请日：2015-03-05

    申请人： Mitsubishi Electric Corporation

    发明人： Toshihide Aiba ,  Toshimitsu Nakai

    IPC分类号： G21C17/108 ,  G21C7/36 ,  G21D1/02 ,  G21D3/10

    摘要： A detector signal-processing circuit comprises the following: a current/voltage conversion part that converts the current value of a neutron detector to a voltage value; a variable gain amplification part that performs amplification by a first-step variable gain using a D/A converter; a current level response-use resistance circuit that selects the measurement range in accordance with the voltage value; temperature measurement units for measuring the temperature of the resistance circuit for current level response; a temperature compensation part for commanding gain compensation by the D/A converter on the basis of the measured temperature; and a selective adjustment control part for selective control of the measurement range and adjustment of the variable gain of the variable gain amplification part. Due to this configuration, neutron flux can be measured with high precision while maintaining a constant output precision, before and after switching of the measurement range.

    METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE PROTECTION SYSTEM (ICOPS) USING THE SAME
    63.
    发明申请
    METHOD OF SYNTHESIZING AXIAL POWER DISTRIBUTIONS OF NUCLEAR REACTOR CORE USING NEURAL NETWORK CIRCUIT AND IN-CORE PROTECTION SYSTEM (ICOPS) USING THE SAME 审中-公开
    使用神经网络电路和内核保护系统（ICOPS）合成核反应堆核心轴功率分布的方法

    公开(公告)号：US20160180976A1

    公开(公告)日：2016-06-23

    申请号：US14857712

    申请日：2015-09-17

    申请人： KEPCO Nuclear Fuel Co., Ltd

    发明人： Young Ho Park ,  Young Baek Kim ,  Dong Soo Kim ,  Do Young Oh

    IPC分类号： G21C17/06 ,  G21D3/10 ,  G06N3/08 ,  G06G7/54

    CPC分类号： G21C17/06 ,  G06G7/54 ,  G06N3/088 ,  G21D3/00 ,  G21D3/002 ,  G21D3/10 ,  Y02E30/39

    摘要： There are provided a method of synthesizing axial power distributions of a nuclear reactor core using a neural network circuit and an in-core protection system (ICOPS) using the same, in which using the neural network circuit including an input layer, an output layer, and at least one hidden layer, each layer being configured with at least one node, each node of one layer being connected to nodes of the other layers, node-to-node connections being made with connection weights varied based on a learning result, optimum connection weights between the respective nodes constituting the neural network circuit are determined through learning based on various core design data applied to the design of a nuclear reactor core of a nuclear power plant, and axial power distributions of the nuclear reactor core are synthesized based on ex-core flux detector signals measured by ex-core neutron flux detectors during operation of a nuclear reactor, so that the initial time required to perform a start-up test of the nuclear reactor can be reduced since basic data for synthesizing axial power distributions need not be separately measured in the start-up test of the nuclear reactor contrary to a conventional ICOPS, thereby improving the economic efficiency of the nuclear power plant, and so that overall nuclear reactor core design data can be used rather than actual measurement data in the start-up test (i.e., at the beginning of a period of nuclear fuel), thereby more accurately replicating axial power distributions of the nuclear reactor core throughout the overall period of the nuclear fuel.

    摘要翻译： 提供了一种使用神经网络电路和使用其的核心保护系统（ICOPS）来合成核反应堆堆芯的轴向功率分布的方法，其中使用神经网络电路包括输入层，输出层， 和至少一个隐藏层，每个层被配置有至少一个节点，一个层的每个节点连接到其他层的节点，节点到节点连接是用连接权重进行的，所述连接权重基于学习结果而变化，最优 通过基于应用于核电站核反应堆核心设计的各种核心设计数据的学习来确定构成神经网络电路的各个节点之间的连接权重，并且基于前者合成核反应堆堆芯的轴向功率分布 在核反应堆运行期间由核心中子通量检测器测量的核磁通检测器信号，使得执行起始 - 可以减少核反应堆的上升试验，因为与常规ICOPS相反，在核反应堆的启动试验中不需要单独测量用于合成轴向功率分布的基础数据，从而提高核电厂的经济效率， 因此可以使用整个核反应堆核心设计数据而不是启动试验中的实际测量数据（即在核燃料周期开始时），从而更准确地复制整个核反应堆核心的轴向功率分布 整个核燃料时期。

    METHOD FOR OPERATING NUCLEAR POWER GENERATION PLANT AND NUCLEAR POWER GENERATION PLANT
    64.
    发明申请
    METHOD FOR OPERATING NUCLEAR POWER GENERATION PLANT AND NUCLEAR POWER GENERATION PLANT 审中-公开
    核动力发电厂和核发电厂的运行方法

    公开(公告)号：US20090141847A1

    公开(公告)日：2009-06-04

    申请号：US12324936

    申请日：2008-11-28

    申请人： Tetsushi HINO ,  Masao CHAKI ,  Motoo AOYAMA ,  Takeshi MITSUYASU ,  Yoshihiko ISHII

    发明人： Tetsushi HINO ,  Masao CHAKI ,  Motoo AOYAMA ,  Takeshi MITSUYASU ,  Yoshihiko ISHII

    IPC分类号： G21D3/10 ,  G21C7/08 ,  G21C7/32 ,  G21C7/00

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

    摘要： An method for operating a nuclear power generation plant, comprising the steps of: forming a plurality of control rod patterns by operating a plurality of control rods during a first period of one operation cycle of a reactor including said first period before a point of time when all control rods are completely withdrawn from a core of said reactor and a core flow rate reaches firstly a set core flow rate, and a second period after said point of time, controlling stepwise at least once a temperature of feed water supplied to said reactor based on a different set feed water temperature during a period included in said first period for operating said reactor with a formed same control rod pattern, and continuing feed water temperature control based on said set feed water temperature until said core flow rate reaches a set core flow rate set based on said set feed water temperature.

    摘要翻译： 一种用于操作核发电厂的方法，包括以下步骤：通过在包括所述第一时段的电抗器的一个操作周期的第一周期期间操作多个控制棒来形成多个控制棒图案， 所有控制棒从所述反应器的核心完全取出，并且芯流速率首先达到设定的核心流速，并且在所述时间点之后的第二时间段内，逐步控制供应到所述反应器的给水温度至少一次 在包括在用于以所形成的相同控制杆模式操作所述反应器的所述第一时段期间的不同设定进料水温度下，以及基于所述设定的给水温度继续供水温度控制，直到所述芯流量达到设定的芯流量 基于所述设定的给水温度设定速率。

    Nuclear reactor power supply
    67.
    发明授权
    Nuclear reactor power supply 失效
    核反应堆电源

    公开(公告)号：US4427620A

    公开(公告)日：1984-01-24

    申请号：US231521

    申请日：1981-02-04

    申请人： Bruce M. Cook

    发明人： Bruce M. Cook

    IPC分类号： G21C7/00 ,  F22B35/00 ,  G05B9/03 ,  G21C17/00 ,  G21D3/10

    CPC分类号： G21D3/10 ,  F22B35/004 ,  G05B9/03 ,  Y02E30/40

    摘要： The redundant signals from the sensor assemblies measuring the process parameters of a nuclear reactor power supply are transmitted each in its turn to a protection system which operates to actuate the protection apparatus for signals indicating off-process conditions. Each sensor assembly includes a number of like sensors measuring the same parameters. The protection system has a number of separate protection units, each unit receiving the process signals from the like sensors of each assembly in its turn. The sets of process signals derived from the sensor parameter assemblies are each in its turn transmitted from the protection system to the control system which impresses control signals on the reactor or its components to counteract the tendency for conditions to drift off-normal status requiring operation of the protection system. A parameter signal selector is interposed between the protection system and the control system. This selector prevents a parameter signal of a set of signals, which differs from the other parameter signals of the set by more than twice the allowable variation of the sensors which produce the set, from passing to the control system. The connection between the protection units and the selector is four separate fiber optic channels so that electrical interaction between the protection units and the selector or control system is precluded. The selectors include a pair of signal selection units, one unit sending selected process signals to primary control channels and the other sending selected process signals to back-up control channels. Test signals are periodically impressed on a selected pair of a selected unit and control channels. When test signals are so impressed the selected control channel is disabled from transmitting control signals to the reactor and/or its associated components.

    摘要翻译： 测量核反应堆电源的工艺参数的传感器组件的冗余信号依次被传送到保护系统，该保护系统用于致动保护装置以用于指示脱离工况条件的信号。 每个传感器组件包括测量相同参数的多个相似的传感器。 保护系统具有多个单独的保护单元，每个单元依次接收来自每个组件的类似传感器的过程信号。 从传感器参数组件得到的过程信号集合又从保护系统传输到控制系统，其将反应器或其组件上的控制信号印记在一起，以抵消条件偏离需要操作的正常状态的趋势 保护系统。 参数信号选择器介于保护系统和控制系统之间。 该选择器防止一组信号的参数信号，该组信号与该组的其它参数信号不同，该组信号是产生该组的传感器的许可变化的两倍以上，从传递到控制系统。 保护单元和选择器之间的连接是四个单独的光纤通道，以防止保护单元与选择器或控制系统之间的电气相互作用。 选择器包括一对信号选择单元，一个单元将选择的处理信号发送到主控制信道，另一个单元将所选择的处理信号发送到备用控制信道。 周期性地对所选择的单元和控制通道对上的测试信号施加测试信号。 当测试信号如此印象时，禁止所选择的控制信道将控制信号发送到反应堆和/或其相关组件。

    Method for the fast and accurate identification of core power in nuclear reactors
    68.
    发明授权
    Method for the fast and accurate identification of core power in nuclear reactors 失效
    核反应堆核心能力快速准确识别的方法

    公开(公告)号：US4297581A

    公开(公告)日：1981-10-27

    申请号：US3444

    申请日：1979-01-15

    申请人： William T. Brunson ,  Anthony F. Lexa

    发明人： William T. Brunson ,  Anthony F. Lexa

    IPC分类号： G21C7/36 ,  G21D3/10 ,  G01T3/00

    CPC分类号： G21C7/36 ,  G21D3/10 ,  Y02E30/39

    摘要： A method is disclosed for rapidly and accurately generating an output signal corresponding to the power of a nuclear reactor core. The method comprises generating out of core neutron flux signals at different time intervals and utilizing predetermined relationships therebetween to adjust a more accurate thermal power signal which has a slow response to transient power conditions.

    摘要翻译： 公开了一种快速准确地产生对应于核反应堆堆芯功率的输出信号的方法。 该方法包括以不同的时间间隔产生核心中子通量信号，并利用它们之间的预定关系来调整对瞬态功率条件具有缓慢响应的更准确的热功率信号。

    Method and apparatus for controlling feedwater flow to steam generating device
    69.
    发明授权
    Method and apparatus for controlling feedwater flow to steam generating device 失效

    公开(公告)号：US4290850A

    公开(公告)日：1981-09-22

    申请号：US70819

    申请日：1979-08-29

    申请人： Takashi Omori ,  Takao Sato

    发明人： Takashi Omori ,  Takao Sato

    IPC分类号： G21D3/10 ,  G21C7/00

    CPC分类号： G21D3/10 ,  Y02E30/40

    摘要： A method and an apparatus for controlling feedwater flow to a steam generating device in a tripped condition of the steam generating device are disclosed. The method comprises the steps of arithmetically calculating a first forecast length of time required for the water level in the steam generating device to attain its desired normal operation level on the basis of the detected water level and the rate of variation of the water level when the detected water level in the steam generating device is lower than the desired normal operation level, the detected flow rate of feedwater is larger than that of the main steam, and the rate of water level variation is positive, arithmetically calculating a second forecast length of time required for the flow rate of feedwater to decrease to a predetermined flow rate on the basis of the detected feedwater flow rate, the detected main steam flow rate and a substantially constant rate of variation of the flow rate of feedwater when the detected feedwater flow rate is larger than the detected main steam flow rate, decreasing the level of the output signal of a ramp signal generator at a rate of variation corresponding to the substantially constant rate of feedwater flow rate variation when the time difference obtained by subtracting 1/2 of the second forecast length of time from the first forecast length of time becomes zero or negative, and selecting either the output signal of the water level controller for generating a control output signal on the basis of various input signals applied thereto including an input signal indicative of the flow rate of main steam, an input signal indicative of the flow rate of feedwater, and an input signal indicative of the water level in the steam generating device or the output signal of the ramp signal generator means, which has a lower value than the other, to deliver it as the feedwater flow rate demand signal, whereby the water level in the steam generating device is reliably stabilized at its normal operation level upon disappearance of the transient phenomenon appeared as a result of the trip.