利索-全球专利检索

  1. Login
  2. Sign Up

Search Results

345 records (took 0.023 seconds)

    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

    Applicant: Alain Grossetete

    Inventor： Alain Grossetete

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

    CPC classification number: G21D3/001 ,  G21C7/08 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

    Abstract: 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).

    NON-INTRUSIVE ERROR DETECTION TECHNIQUES FOR CONTROL AND SHUTDOWN ROD POSITION IN NUCLEAR REACTORS
    6.
    发明申请
    NON-INTRUSIVE ERROR DETECTION TECHNIQUES FOR CONTROL AND SHUTDOWN ROD POSITION IN NUCLEAR REACTORS 审中-公开
    核反应堆控制和关闭位置的非侵入式错误检测技术

    公开(公告)号：US20160365161A1

    公开(公告)日：2016-12-15

    申请号：US15247169

    申请日：2016-08-25

    Applicant: Samuel Caylor ,  Hashem M. Hashemian ,  Gregory W. Morton

    Inventor： Samuel Caylor ,  Hashem M. Hashemian ,  Gregory W. Morton

    IPC: G21C17/12 ,  G21D3/00 ,  G21C7/08

    CPC classification number: G21C7/36 ,  G21C7/10 ,  G21C17/00 ,  G21C17/12 ,  G21D3/001 ,  Y02E30/40

    Abstract: Non-intrusive error detection techniques for control and shutdown rod position in nuclear reactors, including methods of monitoring digital rod position indication (DRPI) signals of a DRPI system of a nuclear power plant. The methods include acquiring digital rod position signals at a point between a DRPI display cabinet and a DRPI data cabinet of the DRPI system, and processing the digital rod position signals to identify variations in a signal level and a signal timing of the digital rod position signals to determine rod position errors of the DRPI system.

    Abstract translation: 用于控制和关闭核反应堆中的杆位置的非侵入式误差检测技术，包括监测核电站DRPI系统的数字杆位置指示（DRPI）信号的方法。 这些方法包括在DRPI显示柜和DRPI系统的DRPI数据柜之间的点处获取数字杆位置信号，以及处理数字杆位置信号，以识别数字杆位置信号的信号电平和信号定时的变化 以确定DRPI系统的杆位置误差。

    METHOD FOR OPERATING A PRESSURIZED WATER REACTOR DURING LOAD MONITORING
    7.
    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

    Applicant: Alain GROSSETETE

    Inventor： Alain GROSSETETE

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

    CPC classification number: G21D3/001 ,  G21C7/08 ,  G21C7/22 ,  G21D3/10 ,  G21D3/16 ,  Y02E30/32 ,  Y02E30/39

    Abstract: 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).

    Abstract translation: 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。

    COMPACT NUCLEAR REACTOR
    8.
    发明申请
    COMPACT NUCLEAR REACTOR 审中-公开
    紧凑型核反应堆

    公开(公告)号：US20150243377A1

    公开(公告)日：2015-08-27

    申请号：US14665341

    申请日：2015-03-23

    Applicant: Babcock & Wilcox Nuclear Energy, Inc.

    Inventor： John D. Malloy ,  Mathew W. Ales

    IPC: G21C1/32 ,  G21C1/08 ,  G21C7/08

    CPC classification number: G21C1/322 ,  G21C1/086 ,  G21C7/08 ,  G21C15/243 ,  Y02E30/32 ,  Y02E30/39

    Abstract: A pressurized water nuclear reactor (PWR) includes a once through steam generator (OTSG) disposed in a generally cylindrical pressure vessel and a divider plate spaced apart from the open end of a central riser. A sealing portion of the pressure vessel and the divider plate define an integral pressurizer volume that is separated by the divider plate from the remaining interior volume of the pressure vessel. An internal control rod drive mechanism (CRDM) has all mechanical and electromagnetomotive components including at least a motor and a lead screw disposed inside the pressure vessel. Optionally CRDM units are staggered at two or more different levels such that no two neighboring CRDM units are at the same level. Internal primary coolant pumps have all mechanical and electromagnetomotive components including at least a motor and at least one impeller disposed inside the pressure vessel. Optionally, the pumps and/or CRDM are arranged below the OTSG

    Abstract translation: 加压水核反应堆（PWR）包括设置在大致圆柱形的压力容器中的一次性蒸汽发生器（OTSG）和与中央提升管的开口端间隔开的分隔板。 压力容器和分隔板的密封部分限定了由分隔板与压力容器的剩余内部容积隔开的整体加压器体积。 内部控制杆驱动机构（CRDM）具有至少包括设置在压力容器内部的电动机和导螺杆的所有机械和电动汽车部件。 可选地，CRDM单元在两个或更多个不同级别交错，使得没有两个相邻的CRDM单元处于相同的水平。 内部主冷却剂泵具有所有机械和电动汽车部件，其包括至少一个电动机和至少一个设置在压力容器内的叶轮。 可选地，泵和/或CRDM布置在OTSG的下方

    Method of achieving automatic axial power distribution control
    9.
    发明授权
    Method of achieving automatic axial power distribution control 有权
    实现自动轴向配电控制的方法

    公开(公告)号：US08699653B2

    公开(公告)日：2014-04-15

    申请号：US13279596

    申请日：2011-10-24

    Applicant: Keith J. Drudy ,  Norman P. Mueller ,  Elijah A. Richter

    Inventor： Keith J. Drudy ,  Norman P. Mueller ,  Elijah A. Richter

    IPC: G21C7/117 ,  G21C7/08 ,  G21C7/36 ,  G21C7/00

    CPC classification number: G21C7/08 ,  G21D3/001 ,  Y02E30/39

    Abstract: A control strategy for a pressurized water nuclear reactor that employs separate, independent control rod banks for respectively controlling Tavg and axial offset within corresponding deadbands. The strategy does not permit the control banks controlling reactor core power and the control banks controlling axial offset to move together, but normally gives preference to the control banks controlling the Tavg except when a demand signal is received simultaneously by both independent control rod banks to move in a same direction, in which case, the control bank compensating for the axial offset is given preference.

    Abstract translation: 压力水核反应堆的控制策略采用独立的，独立的控制棒组，分别控制相应死区内的Tavg和轴向偏移。 该策略不允许控制反应堆堆芯功率的控制组和控制轴偏移的控制组一起移动，但通常优先控制控制组件的控制组，除非同时由独立的控制棒组移动需求信号 在相同的方向上，在这种情况下，给予偏置轴偏移的控制组。

Patent Agency Ranking