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    • 1. 发明授权
    • Feed water heating system for power-generating plant
    • 发电厂给水加热系统
    • US6109037A
    • 2000-08-29
    • US126416
    • 1998-07-30
    • Kenji KumagaiTadashi NarabayashiMikihide NakamaruYutaka AsanumaMakoto YasuokaMichitsugu MoriShuichi Ohmori
    • Kenji KumagaiTadashi NarabayashiMikihide NakamaruYutaka AsanumaMakoto YasuokaMichitsugu MoriShuichi Ohmori
    • F01K9/00F04F5/26F04F5/46F04F5/54F22D1/28F22D1/32F22D11/02G21D5/06F01K13/00
    • G21D5/06F04F5/26F04F5/461F04F5/467F04F5/54F22D1/28F22D11/02
    • A feed water heating system for heating a feed water for a power-generating plant having a steam turbine, a condenser and a steam generator, comprises: a steam injector unit for receiving a plurality of bled steams having different pressures extracted from the steam turbine and an effluent water discharged from the condenser to mix the effluent water with the plurality of bled steams to raise the temperature and pressure of a mixture of the effluent water with the plurality of bled steams to deaerate and discharge the temperature and pressure raised mixture. The steam injector unit comprises: a multistage steam injector having a plurality of steam injectors connected in series for receiving one of the plurality of bled steams and a feed water to mix the one of the plurality of bled steams with the feed water to raise the temperature and pressure of a mixture of the one of the plurality of bled steams and the feed water to discharge the temperature and pressure raised mixture; a cylindrical container for housing therein the multistage steam injector; and a jet centrifugal deaerator, provided downstream of the multistage steam injector, for receiving a feed water discharged from the multistage steam injector and the bled steams to apply a centrifugal force to the feed water and the bled steams to deaerate the feed water to spatially separate a deaerated feed water from the bled steams to discharge the deaerated feed water.
    • 一种用于加热具有蒸汽轮机,冷凝器和蒸汽发生器的发电厂的给水的给水加热系统,包括:蒸汽喷射器单元,用于接收从蒸汽涡轮机提取的具有不同压力的多个排放的蒸汽, 从冷凝器排出的流出水与多个排放的水混合以提高出水与多个排放的蒸汽的混合物的温度和压力,以使温度和压力升高的混合物脱气和排出。 蒸汽喷射器单元包括:多级蒸汽喷射器,其具有串联连接的多个蒸汽喷射器,用于接收多个排放的蒸汽中的一个,以及供给水,以将多个排放的蒸汽中的一个与进料水混合以提高温度 以及所述多个排放蒸汽中的一个和所述给水的混合物的压力以排出所述温度和压力升高的混合物; 用于容纳多级蒸汽喷射器的圆柱形容器; 以及设置在所述多级蒸汽喷射器下游的喷射离心除气器,用于接收从所述多级蒸汽喷射器排出的进料水和所述排放的蒸汽,以向所述进料水和所述排放的蒸汽施加离心力以使所述给水脱气以在空间上分离 来自排放的蒸汽的脱气的给水排出脱气的给水。
    • 3. 发明授权
    • Apparatus for measuring power of nuclear reactor and method for
manufacturing the same
    • 用于测量核反应堆功率的装置及其制造方法
    • US5473644A
    • 1995-12-05
    • US209072
    • 1994-03-11
    • Makoto YasuokaNaotaka Oda
    • Makoto YasuokaNaotaka Oda
    • G21C17/10G21C17/112G21C17/00
    • G21C17/112G21Y2002/204G21Y2002/206G21Y2002/302G21Y2004/30
    • An apparatus for measuring the power of a nuclear reactor having a sensor assembly disposed in a core section inside the nuclear reactor. The sensor assembly includes a cover tube made of metal and press-fitted on the outer surface of a rod-shaped core tube made of metal, a plurality of annular gaps defined between the cover tube and the core tube at different positions spaced from each other in the axial direction of the core tube, a plurality of axial grooves formed in the core tube while opening on the outer surface of the core tube and extending in the axial direction of the core tube, and a plurality of temperature sensors individually guided in the axial grooves and disposed on the core tube. The temperature sensors of the sensor assembly detect temperature distribution in portions of the core tube which face the annular gaps so as to measure the power of the nuclear reactor. By virtue of the above construction, the apparatus can be manufactured easily, has high precision of temperature measurement, and has a sufficiently high reliability for reducing problems such as disconnection and insulation failure.
    • 一种用于测量具有设置在核反应堆内的核心部分中的传感器组件的核反应堆的功率的装置。 传感器组件包括由金属制成的盖管,并压配合在由金属制成的棒状芯管的外表面上,在彼此间隔开的不同位置处限定在盖管和芯管之间的多个环形间隙 在所述芯管的轴向上形成有多个轴向槽,所述多个轴向槽形成在所述芯管中,同时在所述芯管的外表面上开口并在所述芯管的轴向方向上延伸;以及多个温度传感器, 轴向槽,并设置在芯管上。 传感器组件的温度传感器检测芯管的面对环形间隙的部分中的温度分布,以便测量核反应堆的功率。 通过上述结构,可以容易地制造设备,具有高的温度测量精度,并且具有足够高的可靠性,以减少诸如断开和绝缘故障的问题。