Method For Estimating A Future Value Of A Physical Quantity Of An Industrial System Such As A Nuclear Reactor

    公开(公告)号:US20240282472A1

    公开(公告)日:2024-08-22

    申请号:US18380899

    申请日:2023-10-17

    IPC分类号: G21C17/02 G01M99/00

    CPC分类号: G21C17/02 G01M99/005

    摘要: A method for estimating a quantity of a system includes the following steps:



    for each variable of a plurality of variables, obtaining a sequence of successive measurements,
    determining a sequence of successive values of a stability parameter, the parameter being a weighted sum of rates of variation of the variables,
    identifying a time interval in which the stability parameter is less than or equal to a predetermined threshold for a duration greater than or equal to a predetermined duration,
    estimating a sequence of successive estimates of a particular variable, a start time of the sequence being included in the time interval,
    comparing the sequence of estimates and the sequence of measurements, in order to determine an adjustment parameter, and
    estimating the physical quantity of the system using the adjustment parameter.

    MIXING SYSTEM
    2.
    发明申请
    MIXING SYSTEM 审中-公开
    混合系统

    公开(公告)号:US20130148771A1

    公开(公告)日:2013-06-13

    申请号:US13817706

    申请日:2011-08-09

    IPC分类号: G21C15/00 G21C17/02

    摘要: A mixing system including: a backup heater which increases an internal pressure of a pressurizer; a spray valve which decreases the internal pressure of the pressurizer; a pressure sensor which detects the pressure inside the pressurizer; and a pressure control unit which performs a feedback control on a spray valve so that the pressure becomes a target pressure based on a detection pressure value detected by the pressure sensor, wherein the pressure control unit includes a PID control unit which performs a feedback control when heating the coolant by the backup heater and outputs a pressure controller signal and a bias setting unit which sets a bias toward the operation side of the spray valve with respect to the pressure controller signal, and wherein the spray valve is operated based on the pressure controller signal subjected to the setting of the bias.

    摘要翻译: 一种混合系统,包括:备用加热器,其增加加压器的内部压力; 一个降低加压器内部压力的喷雾阀; 压力传感器,其检测所述加压器内的压力; 以及压力控制单元,其对喷雾阀执行反馈控制,使得压力基于由压力传感器检测到的检测压力值成为目标压力,其中压力控制单元包括PID控制单元,其执行反馈控制, 通过备用加热器加热冷却剂,并输出压力控制器信号和偏置设定单元,其相对于压力控制器信号朝向喷射阀的操作侧设定偏压,并且其中喷雾阀基于压力控制器 信号经过偏置设定。

    MONITORING METHOD AND MONITORING PROGRAM FOR BOILING WATER REACTOR, AND ACOUSTIC DAMPING METHOD FOR BOILING WATER REACTOR
    3.
    发明申请
    MONITORING METHOD AND MONITORING PROGRAM FOR BOILING WATER REACTOR, AND ACOUSTIC DAMPING METHOD FOR BOILING WATER REACTOR 失效
    锅炉水反应器监测方法与监测方案及水力反应器的消声阻尼方法

    公开(公告)号:US20110280358A1

    公开(公告)日:2011-11-17

    申请号:US13192606

    申请日:2011-07-28

    IPC分类号: G21C17/00 G21C9/004

    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。

    Method and apparatus of estimating dryout properties in a nuclear light water reactor
    4.
    发明授权
    Method and apparatus of estimating dryout properties in a nuclear light water reactor 有权
    估计核轻水反应堆的干燥性能的方法和装置

    公开(公告)号:US07760842B2

    公开(公告)日:2010-07-20

    申请号:US11512938

    申请日:2006-08-29

    IPC分类号: G21C9/00

    摘要: The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at least a first and a second factor. The first factor is a first function that describes how the dryout property depends on the flow of the cooling medium through the nuclear fuel arrangement. The second factor is a second function that describes how the dryout property depends on the axial power profile of the nuclear fuel arrangement. The first and the second functions describe said flow dependence and said axial power profile dependence independently of each other. The invention also concerns a nuclear energy plant, a computer program product (23) and a method of operating a nuclear energy plant.

    摘要翻译: 本发明涉及一种在沸水反应堆类型的核水反应堆中估计何时可能出现干燥的方法。 该方法包括使用表达核反应堆的局部干燥性质的配方。 该公式包括至少第一和第二因素。 第一个因素是描述干燥特性如何依赖于通过核燃料装置的冷却介质的流动的第一个功能。 第二个因素是第二个功能,描述了干燥特性如何依赖于核燃料装置的轴向功率分布。 第一和第二功能描述了彼此独立的所述流动依赖性和所述轴向功率分布依赖性。 本发明还涉及核能装置,计算机程序产品(23)和操作核能装置的方法。

    METHOD AND APPARATUS OF ESTIMATING DRYOUT PROPERTIES IN A NUCLEAR LIGHT WATER REACTOR
    5.
    发明申请
    METHOD AND APPARATUS OF ESTIMATING DRYOUT PROPERTIES IN A NUCLEAR LIGHT WATER REACTOR 有权
    估计核能水反应器干燥性能的方法和装置

    公开(公告)号:US20100158185A1

    公开(公告)日:2010-06-24

    申请号:US11512938

    申请日:2006-08-29

    IPC分类号: G21C17/00

    摘要: The invention concerns a method of estimating when dryout may occur in a nuclear light water reactor of the boiling water reactor kind. The method includes the use of a formula which expresses the local dryout property of the nuclear reactor. The formula includes at least a first and a second factor. The first factor is a first function that describes how the dryout property depends on the flow of the cooling medium through the nuclear fuel arrangement. The second factor is a second function that describes how the dryout property depends on the axial power profile of the nuclear fuel arrangement. The first and the second functions describe said flow dependence and said axial power profile dependence independently of each other. The invention also concerns a nuclear energy plant, a computer program product (23) and a method of operating a nuclear energy plant.

    摘要翻译: 本发明涉及一种在沸水反应堆类型的核水反应堆中估计何时可能出现干燥的方法。 该方法包括使用表达核反应堆的局部干燥性质的配方。 该公式包括至少第一和第二因素。 第一个因素是描述干燥性能如何依赖于通过核燃料装置的冷却介质的流动的第一个功能。 第二个因素是第二个功能,描述了干燥特性如何依赖于核燃料装置的轴向功率分布。 第一和第二功能描述了彼此独立的所述流动依赖性和所述轴向功率分布依赖性。 本发明还涉及核能装置,计算机程序产品(23)和操作核能装置的方法。

    Method and apparatus for continuous monitoring and control of neutron absorption properties of chemical shim
    9.
    发明授权
    Method and apparatus for continuous monitoring and control of neutron absorption properties of chemical shim 失效
    连续监测和控制化学吸收中性吸收性能的方法与装置

    公开(公告)号:US3578562A

    公开(公告)日:1971-05-11

    申请号:US3578562D

    申请日:1968-10-23

    申请人: COMBUSTION ENG

    CPC分类号: G21C7/22 G21C17/02 Y02E30/39

    摘要: AN APPARATUS, AND METHOD OF OPERATION THEREOF, TO CONTINUOUSLY MONITOR AND CONTROL THE NEUTRON ABSORPTION PROPERTIES OF CHEMICAL SHIM USED IN REGULATING REACTIVITY OF A PRESSURIZED WATER NUCLEAR REACTOR. COOLANTMODERATOR FLUID, INCLUDING THE SOLUBLE NEUTRON ABSORPTION PROPERTY IN THE CHEMICAL SHIM, IS CONTINUOUSLY PASSED THROUGH A CHAMBER HAVING PLURAL NEUTRON DETECTORS SURROUNDING A NEUTRON SOURCE OF KNOWN STRENGTH. UTILIZING THE NEUTRON ABSORPTIOMETRY PRINCIPLE, A SIGNAL REPRESENTATIVE OF THE CONCENTRATION OF THE ABSORPTION PROPERTIES OF THE CHEMICAL SHIM IN THE COOLANT-MODERATOR IS DERIVED. THIS SIGNAL IS THEN APPLIED THROUGH SIGNAL CONDITIONING MEANS TO A READOUT AND ALARM DEVICE SO THAT CONSTANT MONITORING OF THE SHIM CONCENTRATION ABSORTPION PROPERTIES MAY BE ACCOMPLISHED; ADDITIONALLY, THE SIGNAL MAY BE APPLIED TO MAINTAIN THE CONCENTRATION OF NEUTRON ABSORPTION PROPERTIES OF THE CHEMICAL SHIM IN THE COOLANTMODERATOR AT A DESIRED LEVEL.