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    • 3. 发明授权
    • System and method for controlling operation of boiling water reactor
    • 沸水反应堆运行控制系统及方法
    • US4400343A
    • 1983-08-23
    • US085686
    • 1979-10-17
    • Masayuki IzumiRenzo Takeda
    • Masayuki IzumiRenzo Takeda
    • G21D3/14G21C7/32
    • G21D3/14Y02E30/40
    • The pressure P.sub.R in the reactor pressure vessel, the flow rate W.sub.c of the cooling water flowing through the core in the reactor pressure vessel, and the flow rate W.sub.STM of the steam supplied from the reactor pressure vessel to the turbine are detected. The enthalpy H.sub.f of the saturated cooling water is determined on the basis of the pressure P.sub.R. The values of the cooling water flow rate W.sub.c, the steam flow rate W.sub.STM, the enthalpy H.sub.f of the saturated cooling water and a predetermined enthalpy H.sub.IN of the cooling water at the core inlet are substituted into the equation below thereby to obtain the enthalpy H.sub.fw of the feed water. ##EQU1## An error is determined between the feed-water enthalpy H.sub.fw thus obtained and the enthalpy T.sub.fw of the feed water actually supplied into the reactor pressure vessel, and on the basis of this error, the opening of the flow rate control valve on the turbine bleeding pipe is adjusted, so that the flow rate of the steam bled from the turbine for heating the feed water is adjusted according to the error.
    • 检测反应堆压力容器中的压力PR,流过反应堆压力容器中的芯的冷却水的流量Wc以及从反应堆压力容器供给到涡轮的蒸汽的流量WSTM。 基于压力PR确定饱和冷却水的焓Hf。 将冷却水流量Wc,蒸汽流量WSTM,饱和冷却水的焓Hf和核心入口处的冷却水的预定焓HIN的值代入下面的等式,由此获得焓Hfw 给水。 在这样获得的给水焓Hfw与实际供应到反应堆压力容器中的进料水的焓Tfw之间确定误差,并且基于该误差,流量控制阀在 涡轮排气管被调节,从而根据误差调节从涡轮机排出的用于加热给水的蒸汽的流量。
    • 4. 发明授权
    • Load control system for nuclear power plant
    • 核电厂负荷控制系统
    • US4472345A
    • 1984-09-18
    • US286513
    • 1981-07-24
    • Junichi TanjiMasayuki Izumi
    • Junichi TanjiMasayuki Izumi
    • G21D3/12G21D3/14G21C7/00
    • G21D3/14Y02E30/40
    • A load control system for a boiling water reactor power plant. A recirculating pump speed demand signal and a total steam flow demand signal are derived on the basis of combination of a first control signalproduced in accordance with a power difference signal representative of difference between an actual value of an output power of an electric generator and a set value for the generator output and a second control signal produced in accordance with a pressure difference signal representative of difference between an actually measured value of the reactor pressure and a set value therefor. Speed of a recirculating pump is controlled in dependence on the recirculating pump speed demand signal, while opening degrees of a governor valve and a bypass valve of a turbine are controlled in accordance with the total steam flow demand signal. The recirculating pump speed demand signal and the total steam flow demand signal are derived by combining the first or the second control signal which has been regulated through gain elements. Further, the power difference signal is added to the pressure difference signal for modifying the set point for the reactor pressure.
    • 沸水反应堆发电厂负荷控制系统。 基于根据表示发电机的输出功率的实际值与设定值之间的差异的功率差信号产生的第一控制信号的组合导出循环泵速度需求信号和总蒸汽流量需求信号, 并且根据代表反应堆压力的实际测量值与其设定值之间的差异的压力差信号产生的第二控制信号。 根据循环泵速度需求信号来控制循环泵的转速,同时根据总蒸汽流量需求信号控制涡轮机的调速阀和旁通阀的开度。 通过组合通过增益元件调节的第一或第二控制信号来导出循环泵速度需求信号和总蒸汽流量需求信号。 此外,功率差信号被添加到用于修改反应堆压力的设定点的压力差信号。
    • 5. 发明授权
    • Method of controlling operation of nuclear reactor
    • 控制核反应堆运行的方法
    • US4368171A
    • 1983-01-11
    • US210168
    • 1980-11-25
    • Hiromi MaruyamaMasayuki IzumiSadao UchikawaRenzo Takeda
    • Hiromi MaruyamaMasayuki IzumiSadao UchikawaRenzo Takeda
    • G21C7/00G21C7/08
    • G21C7/00G21Y2002/201G21Y2004/40Y02E30/39
    • A method of operating a nuclear reactor adapted to use cross-shaped control rods. The control rods are grouped into a plurality of groups having a first group consisting of a control rod located at the center of the core, a second group consisting of 8 control rods surrounding the control rod of the first group, a third group consisting of control rods located adjacent to and outside of the control rods of the second group, and other groups determined successively in the same manner as in the third group. During the operation period other than the period in which the number of the control rods to be inserted for realizing the critical condition of said nuclear reactor is less than 6, the nuclear reactor is operated with control rod patterns in which the inserted control rods are selected from control rods of alternate or every other groups of said groups so as to include at least a pair of control rods which are located in a similar manner to that of the KNIGHT's movement on a chess board.
    • 一种操作适于使用十字形控制棒的核反应堆的方法。 控制杆被分组成多个组,其具有第一组,第一组由位于芯的中心的控制棒组成,第二组由围绕第一组的控制棒的8个控制棒组成,第三组包括控制 位于第二组的控制棒附近和外侧的杆,以及与第三组相同的方式连续确定的其他组。 在操作期间,为了实现上述核反应堆的临界状态而插入的控制杆的数量少于6的期间,核反应堆以选择插入的控制棒的控制杆模式进行操作 从所述组的交替或其他组的控制棒中,至少包括一对控制棒,其以类似于在棋盘上的KNIGHT的运动的方式定位。