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公开(公告)号：US09728283B2
公开(公告)日：2017-08-08
申请号：US15219530
申请日：2016-07-26
CPC分类号： G21C17/12 , G01D5/04 , G01D5/2033 , G21C7/12 , G21Y2002/204 , G21Y2004/30 , H02K35/02 , Y02E30/39
摘要： A cam is immersed in water at an elevated temperature and/or pressure. A reciprocating cam follower also immersed in the water contacts a surface of the cam. The cam follower includes a permanent magnet. An electrically conductive coil is magnetically coupled with the permanent magnet such that movement of the cam follower induces an electrical signal in the electrically conductive coil. A sealed housing also immersed in the water contains the electrically conductive coil and seals it from contact with the water. Leads of the coil are electrically accessible from outside the sealed housing and from outside the water. Alternatively, the cam includes magnetic inserts, the cam follower is replaced by a sensor arm of magnetic material, and the sensor arm and/or the inserts are magnetized whereby rotation of the rotary element causes time modulation of the magnetic coupling and induces coil voltage.
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公开(公告)号：US09697916B2
公开(公告)日：2017-07-04
申请号：US12351748
申请日：2009-01-09
申请人： Brent D. Shumaker , Hashem M. Hashemian , Gregory W. Morton , Danny D. Beverly , Casey D. Sexton
发明人： Brent D. Shumaker , Hashem M. Hashemian , Gregory W. Morton , Danny D. Beverly , Casey D. Sexton
IPC分类号： G21C17/00
CPC分类号： G21C17/00 , G21C7/08 , G21C17/12 , G21Y2002/204 , Y02E30/39
摘要： An automated system for on-line monitoring and coil diagnostics of rod position indicator (RPI) coils coil diagnostic, or RPI coil diagnostic system. The RPI coil diagnostic system performs coil diagnostics for a RPI system in a nuclear power plant. The RPI coil diagnostic system is in electrical communication with and monitors the outputs of the detector coils. The RPI coil diagnostic system measures characteristics of the detector coils that are indicative of the health of the detector coils and/or the connections between the detector coils and the RPI electronics.
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公开(公告)号：US09691508B2
公开(公告)日：2017-06-27
申请号：US12925940
申请日：2010-11-02
摘要： A method for determining a state of operational readiness of a fuel cell backup system of a nuclear reactor system includes monitoring a readiness state of a fuel cell system associated with a nuclear reactor system, and providing a readiness determination of the fuel cell system by comparing the monitored state of readiness of the fuel cell system to an established operating readiness state, the established operating readiness state a function of at least one characteristic of the nuclear reactor system. An apparatus includes a fuel cell monitoring system configured to monitor a readiness state of a fuel cell system associated with a nuclear reactor system, and a readiness determination system configured to provide a readiness determination of the fuel cell system by comparing the monitored state of readiness of the fuel cell system to an established operating readiness state.
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公开(公告)号：US09657588B2
公开(公告)日：2017-05-23
申请号：US14140634
申请日：2013-12-26
发明人： Mahesh Raveendranatha Panicker , Ajay Kumar Behera , Venkatesh Rajagopalan , Venkatarao Ryali , Vivek Venugopal Badami , Budhaditya Hazra
CPC分类号： F01D21/003 , F05D2260/80 , F05D2270/304 , F05D2270/80
摘要： A system for monitoring health of a rotor is presented. The system includes a processing subsystem that generates a measurement matrix based upon a plurality of resonant-frequency first delta times of arrival vectors corresponding to a blade and a first sensing device, and a plurality of resonant-frequency second delta times of arrival vectors corresponding to the blade and a second sensing device, generates a resonant matrix based upon the measurement matrix such that entries in the resonant matrix are substantially linearly uncorrelated and linearly independent, and generates a resonance signal using a first subset of the entries of the resonant matrix, wherein the resonance signal substantially comprises common observations and components of the plurality of resonant-frequency first delta times of arrival vectors and the plurality of resonant-frequency second delta times of arrival vectors.
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35.发明申请公开(公告)号：US20170103821A1
公开(公告)日：2017-04-13
申请号：US15287667
申请日：2016-10-06
IPC分类号： G21C17/00
摘要： A submersible system and method for measuring the gas volume fraction in an aerated fluid inside a reactor (1) wherein the aerated fluid is composed by gas dispersed in the form of bubbles in a fluid in the form of a solution, suspension, mixture of liquids or a combination thereof, which comprises: an open and pass-through gas exclusion device (20) of a variable cross section wherein the inlet opening whereby the fluid enters without gas bubbles towards the opened and through gas bubbles exclusion device (20) is greater than the outlet opening whereby the fluid exits without gas bubbles of the opened and through gas bubble exclusion device (20), wherein said outlet opening abuts with an inlet pipe (23), a sealed camera (24) which comprises a flow measurement means, which contains at least one flow meter allowing to measure the gas-free fluid velocity when circulating between an inlet (27) of said sealed camera (24) and an outlet (28) of said sealed camera (24), wherein said inlet (27) of said sealed camera (24) is coupled to said inlet pipe (23) and wherein said outlet (28) of said sealed camera (24) is coupled to an outlet pipe (26) of the liquid dispersion towards the reactor (1); a flow transmitter (29) connected to said flow meter, located inside or outside said sealed camera (24), wherein said transmitter (29) generates an outlet signal proportional to the bubbles-free fluid velocity through a gas bubble exclusion cell and a calculation unit (30) which generates an output signal (31) proportional to the gas volume fraction in the aerated fluid.
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36.发明授权Critical heat flux prediction device, critical heat flux prediction method and safety evaluation system 有权临界热通量预测装置，临界热通量预测方法和安全评估系统公开(公告)号：US09576689B2
公开(公告)日：2017-02-21
申请号：US13820294
申请日：2011-08-12
申请人： Tadakatsu Yodo
发明人： Tadakatsu Yodo
IPC分类号： G21C17/00 , G21D3/04 , G21C7/32 , G21C17/112
CPC分类号： G21D3/04 , G21C7/32 , G21C17/00 , G21C17/02 , G21C17/038 , G21C17/112 , Y02E30/39
摘要： A critical heat flux prediction device, a critical heat flux prediction method, a safety evaluation system, and a core monitoring system using the safety evaluation system can predict critical heat flux in a core of a reactor with a high degree of accuracy by obtaining a correlation plot distribution representing a relation of critical heat flux on a thermal equilibrium quality based on experimental data, approximating a correlation plot distribution through a logistic function that is a model function in which critical heat flux is expressed by a function of a thermal equilibrium quality, and obtaining a critical heat flux correlation of critical heat flux and a thermal equilibrium quality.
摘要翻译： 临界热通量预测装置，临界热通量预测方法，安全评估系统和使用安全评估系统的核心监测系统可以通过获得相关性来高精度地预测反应堆核心的临界热通量 基于实验数据表示临界热通量对热平衡质量的关系的曲线分布，通过作为其中临界热通量由热平衡质量的函数表示的模型函数的逻辑函数近似相关图分布，以及 获得临界热通量和热平衡质量的临界热通量相关性。
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37.发明申请ASYMMETRIC FILTER OF NEUTRON SIGNALS FOR DETECTING POWER OSCILLATIONS IN BOILING WATER REACTORS 审中-公开用于检测锅炉水反应堆功率振荡的中子信号不对称滤波器公开(公告)号：US20170040072A1
公开(公告)日：2017-02-09
申请号：US14817183
申请日：2015-08-03
申请人： YOUSEF M. FARAWILA
发明人： YOUSEF M. FARAWILA
IPC分类号： G21C17/00
CPC分类号： G21C7/36 , G21C17/108 , G21D3/001 , Y02E30/31 , Y02E30/39
摘要： This invention introduces a new method for detecting power oscillations that may occur in Boiling Water Reactor (BWR) cores. According to this invention, the Average Power Range Monitor (APRM) is enabled to detect power oscillations even when the signals from the Local Power Range Monitors (LPRMs) that make up the APRM signal are not in-phase and tend to cancel out. The asymmetric filtering algorithm that is the core of this invention is applied to the individual LPRM signals before they are summed up to make a new APRM signal. The new APRM signal will increase when oscillations occur, regardless of the instability type, and can thus be used for detecting reactor instability and enable the operator or automatic reactor protection systems to actuate and prevent reactor fuel damage.
摘要翻译： 本发明引入了一种用于检测沸腾反应堆（BWR）核心中可能发生的功率振荡的新方法。 根据本发明，即使来自构成APRM信号的本地功率范围监视器（LPRM）的信号不是同相并且倾向于抵消，平均功率范围监视器（APRM）也能够检测功率振荡。 作为本发明核心的非对称滤波算法在将它们相加之前被应用于各个LPRM信号以产生新的APRM信号。 无论不稳定类型如何，当发生振荡时，新的APRM信号将增加，因此可用于检测反应堆不稳定性，并使操作员或自动反应堆保护系统能够起动并防止反应堆燃料损坏。
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38.发明授权公开(公告)号：US09562843B2
公开(公告)日：2017-02-07
申请号：US14553463
申请日：2014-11-25
发明人： Young-Suk Kim , Sung-Soo Kim , Dae-Whan Kim
CPC分类号： G01N17/006 , G01N33/20 , G21C17/00 , G21C19/207
摘要： A method of non-destructive evaluation of stress corrosion cracking of structural components made of metal alloys, and a method of evaluation of the remaining lifetime of the structural component made of metal alloys are provided, in which a change in properties of the structural components made of metal alloys being used in operating nuclear power plants is measured according to the degree of atomic ordering (or short range ordering) of alloying atoms, and stress corrosion cracking of the structural components made of metal alloys is thus evaluated. The properties to be measured may be one or more selected from a group consisting of hardness, electrical resistivity and thermal conductivity.
摘要翻译： 提供了一种由金属合金制成的结构部件的应力腐蚀开裂的非破坏性评价方法以及由金属合金构成的结构部件的剩余寿命的评价方法，其特征在于， 根据合金原子的原子排列程度（或短程排序）来测量用于运行核电站的金属合金，从而评估由金属合金制成的结构部件的应力腐蚀开裂。 要测量的性质可以是选自由硬度，电阻率和导热性组成的组中的一种或多种。
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公开(公告)号：US20160349385A1
公开(公告)日：2016-12-01
申请号：US14884177
申请日：2015-10-15
发明人： Masaki TAGUCHI , Kenichi MOTEKI
CPC分类号： G21C17/112 , G01T1/00 , G01T7/00 , G21C17/00 , G21D3/06
摘要： The radiation monitor includes: a shutter; a calculation section; an AC solenoid; a temperature switch which is attached to the AC solenoid; a circuit protector which has a contact and is connected in series to the AC solenoid; and a mode selection switch connected in series to the AC solenoid. The shutter is maintained in a closed state when the mode selection switch is set to a normal mode; the mode selection switch is changed from the normal mode to a check radiation source mode, thereby flowing an AC current through the AC solenoid to change the shutter from the closed state to an opened state; and the contact of the temperature switch is reversed from the opened state to the closed state, thereby disconnecting the contact of the circuit protector to interrupt the AC current that flows through the AC solenoid.
摘要翻译： 辐射监测器包括：快门; 计算部分; 交流电磁铁; 连接到交流电磁阀的温度开关; 电路保护器，其具有触点并与AC电磁线圈串联连接; 以及与AC电磁阀串联连接的模式选择开关。 当模式选择开关设置为正常模式时，快门保持在关闭状态; 模式选择开关从正常模式改变为检查辐射源模式，从而使交流电流流过AC螺线管，以将快门从关闭状态改变为打开状态; 并且温度开关的触点从打开状态反向关闭状态，从而断开电路保护器的触点以中断通过AC电磁阀流过的交流电流。
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40.发明授权公开(公告)号：US09484120B2
公开(公告)日：2016-11-01
申请号：US14827221
申请日：2015-08-14
发明人： James M. King , Bruce A. W. Smith , Paul Feenstra
摘要： The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube within a calandria tube of a nuclear reactor. The method comprises the steps of: vibrationally isolating a section of the pressure tube; vibrating the wall of said pressure tube within said isolated section; detecting vibration of the wall at a minimum of two axial positions within said isolated sections; and detecting the reduction in vibration level of the wall at one or more of said axial positions in comparison to the remaining axial positions. The apparatus comprises a tool head to be inserted into the pressure tube, the tool head comprising a first end and a second and a clamping block m each of said ends. The clamping blocks are used to vibrationally isolate a section of the pressure tube located between said ends. The apparatus also comprises piezo-actuators operable to vibrate said pressure tube; and accelerometers used for measuring vibration of said pressure tube.
摘要翻译： 本发明提供了一种用于检测和/或重新定位用于将压力管保持在核反应堆的卡兰里德管内的位置的装置。 该方法包括以下步骤：振动隔离压力管的一部分; 在所述隔离部分内振动所述压力管的壁; 在所述隔离部分内的至少两个轴向位置处检测壁的振动; 并且与其余的轴向位置相比较，检测在所述轴向位置的一个或多个处的壁的振动水平的降低。 该装置包括一个待插入压力管的工具头，该工具头包括一个第一端，一个第二和一个夹紧块，每一个端部。 夹紧块用于振动隔离位于所述端部之间的压力管的一部分。 该装置还包括可操作以振动所述压力管的压电致动器; 以及用于测量所述压力管的振动的加速度计。
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