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149 条记录 (耗时 0.018 秒)

    METHOD OF CALIBRATING EXCORE DETECTORS IN A NUCLEAR REACTOR
    92.
    发明申请
    METHOD OF CALIBRATING EXCORE DETECTORS IN A NUCLEAR REACTOR 审中-公开
    在核反应堆中校准检测器的方法

    公开(公告)号：US20110268239A1

    公开(公告)日：2011-11-03

    申请号：US12770870

    申请日：2010-04-30

    申请人： David Jerome Krieg

    发明人： David Jerome Krieg

    IPC分类号： G21C17/108

    CPC分类号： G21C17/108 ,  G21D3/001 ,  G21D3/08 ,  Y02E30/40

    摘要： A method of calibrating excore detectors for a pressurized water reactor (PWR) includes: measuring peripheral core flux signals using excore detectors disposed at a plurality of locations spaced about the periphery of the core, and using the measured power distribution from either a core monitoring system or in-core flux measurement. Calibration of the excore detectors is broken into two parts: (1) the relation between the excore detector signal and weighted peripheral assembly axial offset, and (2) the relation between weighted peripheral assembly axial offset and core average axial offset. Relation (2) can be determined by a representative neutronics model. Accuracy of the neutronics solution is improved by applying nodal calibration factors, which represent the ratio of the measured three-dimensional power distribution to the nodal predicted three-dimensional power distribution and correct the neutronic results to match what would be measured if predictive scenarios were actually performed in the actual reactor core.

    摘要翻译： 用于校准压水反应堆（PWR）的排泄检测器的方法包括：使用设置在围绕芯的周边间隔开的多个位置处的检测器来测量外围核心磁通信号，并且使用来自核心监控系统 或核心内磁通测量。 探测器的校准分为两部分：（1）探测器信号与加权外围组件轴向偏移之间的关系，（2）加权周边组件轴向偏移与芯平均轴向偏移之间的关系。 关系（2）可以通过代表性的中子模型来确定。 通过应用节点校准因子来改善中子解决方案的准确度，这些因子校正因子表示测量的三维功率分布与节点预测的三维功率分布的比值，并校正中子结果以匹配如果预测情景实际上将被测量 在实际反应堆堆芯中进行。

    Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor
    93.
    发明授权
    Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor 有权
    沸水反应堆监测方法和监测程序，沸水反应堆的声阻尼方法

    公开(公告)号：US08009788B2

    公开(公告)日：2011-08-30

    申请号：US11670580

    申请日：2007-02-02

    申请人： Masaya Ohtsuka ,  Kiyoshi Fujimoto ,  Masaaki Tsubaki

    发明人： Masaya Ohtsuka ,  Kiyoshi Fujimoto ,  Masaaki Tsubaki

    IPC分类号： G21C7/00

    CPC分类号： G21C17/00 ,  G21C17/02 ,  G21D3/001 ,  G21D3/08 ,  G21Y2002/201 ,  G21Y2002/207 ,  G21Y2002/303 ,  G21Y2004/40 ,  G21Y2004/403 ,  Y02E30/39

    摘要： A boiling water reactor includes a reactor pressure vessel; a steam pipe for transporting steam generated in the reactor pressure vessel out from a steam dome positioned at an upper part of the reactor pressure vessel; a high pressure turbine connected to the steam pipe and driven by the steam; a feedwater heater which heats feedwater supplied to the reactor pressure vessel using bleed steam flowing from the high pressure turbine to the feedwater heater; 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 boiling water reactor further includes a monitor and control system which controls an opening degree of the bleeding valve based on a magnitude of fluctuating pressure in the main steam line that is detected by the pressure sensor.

    摘要翻译： 沸水反应器包括反应堆压力容器; 蒸汽管，用于将反应堆压力容器中产生的蒸汽从位于反应堆压力容器上部的蒸汽穹顶运出; 连接到蒸汽管并由蒸汽驱动的高压涡轮机; 给水加热器，其使用从高压涡轮机流到给水加热器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。 沸水反应器还包括监测和控制系统，其基于由压力传感器检测的主蒸汽管线中的波动压力的大小来控制排出阀的开度。

    METHODS OF CONTROLLING HYDROGEN CONCENTRATIONS IN AN OFFGAS SYSTEM OF A NUCLEAR REACTOR BY PASSIVE AIR INJECTION
    94.
    发明申请
    METHODS OF CONTROLLING HYDROGEN CONCENTRATIONS IN AN OFFGAS SYSTEM OF A NUCLEAR REACTOR BY PASSIVE AIR INJECTION 有权
    通过被动空气喷射控制核反应堆脱硫系统中氢浓度的方法

    公开(公告)号：US20110158879A1

    公开(公告)日：2011-06-30

    申请号：US12647819

    申请日：2009-12-28

    申请人： Paul Y. Shu ,  John C. Whittaker ,  Angelito Foz Gonzaga ,  Luong C. Tran

    发明人： Paul Y. Shu ,  John C. Whittaker ,  Angelito Foz Gonzaga ,  Luong C. Tran

    IPC分类号： B01D53/46

    CPC分类号： G21D3/04 ,  G21C9/06 ,  G21C19/317 ,  G21D3/08 ,  Y02E30/40

    摘要： Example embodiments relate to methods of controlling hydrogen concentrations in an offgas system of a nuclear reactor by passive air injection. A method according to a non-limiting embodiment may include passively injecting ambient air through the hydrogen water chemistry system into an existing offgas line of the offgas system. The offgas line is configured to transport non-condensable gases, including hydrogen, from a condenser to a recombiner. As a result of the passive air injection, the combined flow of hydrogen and oxygen react in the recombiner to form water vapor, thereby reducing the hydrogen concentration of the offgas exiting the recombiner.

    摘要翻译： 示例性实施例涉及通过被动空气喷射来控制核反应堆的废气系统中的氢浓度的方法。 根据非限制性实施方案的方法可以包括将通过氢水化学系统的环境空气被动地注入到废气系统的现有废气管线中。 排气管线被配置为将不可冷凝的气体（包括氢气）从冷凝器输送到重组器。 作为被动空气注入的结果，氢和氧的组合流在重组器中反应以形成水蒸气，从而降低离开重组器的废气的氢浓度。

    Nuclear reactor system and nuclear reactor control method
    95.
    发明申请
    Nuclear reactor system and nuclear reactor control method 审中-公开
    核反应堆系统和核反应堆控制方法

    公开(公告)号：US20100272223A1

    公开(公告)日：2010-10-28

    申请号：US11657456

    申请日：2007-01-25

    申请人： Atsushi Fushimi ,  Setsuo Arita ,  Yoshihiko Ishii ,  Tomohiko Ikegawa ,  Shin Hasegawa ,  Kazuhiko Ishii

    发明人： Atsushi Fushimi ,  Setsuo Arita ,  Yoshihiko Ishii ,  Tomohiko Ikegawa ,  Shin Hasegawa ,  Kazuhiko Ishii

    IPC分类号： G21C7/36 ,  G21C1/08

    CPC分类号： G21C7/36 ,  G21D3/08 ,  Y02E30/39

    摘要： In order to stably control a nuclear reactor in a short time, so as not to enter an unstable region that is determined by the relationship between the reactor pressure, the reactor power and the subcooling of the core inlet coolant at start-up time, the nuclear reactor system comprises: an power control apparatus for generating a control rod operation signal for operating a control rod, based on the reactor water temperature change rate; a feed water control apparatus for generating a feed water flow rate signal and a discharge water flow rate signals based on the reactor water level signal; and a process computer for performing overall control of the power control apparatus and the feed water control apparatus, wherein the feed water control apparatus has the reactor water temperature change rate setting section for adjusting the reactor water temperature change rate set value based on the variation of the reactor water level signal.

    摘要翻译： 为了在短时间内稳定地控制核反应堆，为了不进入由反应堆压力，反应堆功率和启动时的核心入口冷却剂的过冷度之间的关系确定的不稳定区域， 核反应堆系统包括：功率控制装置，用于基于反应堆水温度变化率产生用于操作控制棒的控制棒操作信号; 用于产生基于反应堆水位信号的给水流量信号和排放水流量信号的给水控制装置; 以及用于执行动力控制装置和给水控制装置的整体控制的处理计算机，其中，给水控制装置具有反应堆水温变化率设定部，其用于基于变化而调整反应堆水温变化率设定值 反应堆水位信号。

    REACTOR POWER CONTROL APPARATUS OF NATURAL CIRCULATION REACTOR AND METHOD FOR CONTROLLING REACTOR POWER OF NATURAL CIRCULATION REACTOR
    99.
    发明申请
    REACTOR POWER CONTROL APPARATUS OF NATURAL CIRCULATION REACTOR AND METHOD FOR CONTROLLING REACTOR POWER OF NATURAL CIRCULATION REACTOR 有权
    自然循环反应器的反应器功率控制装置及自然循环反应器的反应器功率控制方法

    公开(公告)号：US20070201603A1

    公开(公告)日：2007-08-30

    申请号：US11678753

    申请日：2007-02-26

    申请人： Koichi Sato ,  Shin Hasegawa

    发明人： Koichi Sato ,  Shin Hasegawa

    IPC分类号： G21C9/00

    CPC分类号： G21C1/084 ,  G21C7/08 ,  G21D3/08 ,  G21Y2002/207 ,  G21Y2002/304 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

    摘要： In the present invention, a reactor power control apparatus of a natural circulation reactor comprises a reactor pressure vessel which circulates cooling water using the density difference of the coolant inside, a feed water pipe which is connected to the reactor pressure vessel and supplies cooling water, a power control section which controls the reactor power using a control rod. The feed water pipe has an ultrasonic thermometer sensor. Driving of the control rod is controlled by the power control section based on the feed water temperature detected by the feed water thermometer. The reactor power control apparatus can detect the temperature of the feed water and perform drive control of the control rod preferentially, and obtain stable reactor power.

    摘要翻译： 在本发明中，天然循环反应器的反应堆功率控制装置包括使用冷却剂内部的密度差循环冷却水的反应堆压力容器，连接到反应堆压力容器并供给冷却水的给水管， 功率控制部，其使用控制棒来控制反应堆功率。 给水管具有超声波温度计传感器。 控制棒的驱动由功率控制部根据给水温度计检测到的给水温度进行控制。 反应堆功率控制装置可以检测给水温度，优先进行控制棒的驱动控制，获得稳定的反应堆功率。

    Reactor power control apparatus of a natural circulation boiling water reactor and a feed water control apparatus and nuclear power generation plant
    100.
    发明申请
    Reactor power control apparatus of a natural circulation boiling water reactor and a feed water control apparatus and nuclear power generation plant 有权
    自然循环沸水反应堆的反应堆功率控制装置，给水控制装置和核发电厂

    公开(公告)号：US20070201599A1

    公开(公告)日：2007-08-30

    申请号：US11657459

    申请日：2007-01-25

    申请人： Atsushi Fushimi ,  Setsuo Arita ,  Kazuhiko Ishii ,  Yoshihiko Ishii ,  Shin Hasegawa ,  Atsutoshi Mizuide

    发明人： Atsushi Fushimi ,  Setsuo Arita ,  Kazuhiko Ishii ,  Yoshihiko Ishii ,  Shin Hasegawa ,  Atsutoshi Mizuide

    IPC分类号： G21C7/36

    CPC分类号： G21C1/084 ,  G21C7/36 ,  G21D3/08 ,  G21Y2002/201 ,  G21Y2004/30 ,  G21Y2004/40 ,  Y02E30/31 ,  Y02E30/39

    摘要： In order to provide a reactor power control apparatus which can maintain a stable water level when reactivity control based on control rod operation and water level adjustment is performed, this invention comprises a turbine control which calculates the load set error signal from the error between the set target generator power value and the generator power that was fed back and outputs to the turbine control apparatus; control rod control in the natural circulation boiling water reactor which calculates the control rod operation signal and outputs it to the control rod drive control apparatus; water level control inside the natural circulation boiling water reactor which calculates the water level set signal and outputs it to the feed water control apparatus; and the switch determining device which selectively outputs one of the control rod control and water level control based on the generator power that was fed back, the reactor power and water level, as well as switching rules and determination values.

    摘要翻译： 为了提供一种当基于控制杆操作和水位调节进行反应性控制时可以保持稳定的水位的反应堆功率控制装置，本发明包括一个涡轮机控制，该控制装置根据该组中的误差计算负载设定误差信号 目标发电机功率值和反馈并输出到涡轮机控制装置的发电机功率; 控制棒控制在自然循环沸水反应堆中，计算控制棒的运行信号，并将其输出到控制棒驱动控制装置; 自然循环沸水反应堆内的水位控制，其计算水位设定信号并输出​​给给水控制装置; 以及切换判定装置，其基于反馈的发电机功率，反应堆功率和水位以及切换规则和判定值选择性地输出控制棒控制和水位控制中的一个。