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38 条记录 (耗时 0.01 秒)

    METHODS FOR PROTECTION NUCLEAR REACTORS FROM THERMAL HYDRAULIC/NEUTRONIC CORE INSTABILITY
    2.
    发明公开
    METHODS FOR PROTECTION NUCLEAR REACTORS FROM THERMAL HYDRAULIC/NEUTRONIC CORE INSTABILITY 有权
    程序核反应堆前热HU /NEUTRONIKKERNINSTABILITÄT保护

    公开(公告)号：EP2826040A4

    公开(公告)日：2015-11-04

    申请号：EP13798220

    申请日：2013-03-14

    申请人： WESTINGHOUSE ELECTRIC CORP

    发明人： BLAISDELL JOHN A ,  CHU EDWARD M ,  ROTANDER CAMILLA S ,  KUMAR GURIKAR V

    IPC分类号： G21C17/032

    CPC分类号： G21D3/001 ,  G21C17/112 ,  G21D3/04 ,  Y02E30/40

    摘要： The invention relates to methods for protecting a nuclear reactor core, such as a boiling water reactor core, from fuel and cladding damage due to thermal hydraulic instability in extended operating power flow conditions and, in particular, when an extended power uprate is implemented. The methods employ existing licensed stability methodologies and incorporated minor changes, e.g., to the Average Power Range Monitor (APRM)-based trip system to preclude operation inside the stability vulnerable region of the power/flow map. The APRM-based trip system is modified to set down the APRM flow-biased scram line when core flow is less than a predetermined core flow to prevent the core from entering an unstable region of operation.

    METHODS FOR PROTECTION NUCLEAR REACTORS FROM THERMAL HYDRAULIC/NEUTRONIC CORE INSTABILITY
    3.
    发明公开
    METHODS FOR PROTECTION NUCLEAR REACTORS FROM THERMAL HYDRAULIC/NEUTRONIC CORE INSTABILITY 有权
    从水热/中子核不稳定性保护核反应堆的方法

    公开(公告)号：EP2826040A2

    公开(公告)日：2015-01-21

    申请号：EP13798220.3

    申请日：2013-03-14

    申请人： Westinghouse Electric Company LLC

    发明人： BLAISDELL, John, A. ,  CHU, Edward, M. ,  ROTANDER, Camilla, S. ,  KUMAR, Gurikar, V.

    IPC分类号： G21C17/032

    CPC分类号： G21D3/001 ,  G21C17/112 ,  G21D3/04 ,  G21D2003/005 ,  Y02E30/40

    摘要： The invention relates to methods for protecting a nuclear reactor core, such as a boiling water reactor core, from fuel and cladding damage due to thermal hydraulic instability in extended operating power flow conditions and, in particular, when an extended power uprate is implemented. The methods employ existing licensed stability methodologies and incorporated minor changes, e.g., to the Average Power Range Monitor (APRM)-based trip system to preclude operation inside the stability vulnerable region of the power/flow map. The APRM-based trip system is modified to set down the APRM flow-biased scram line when core flow is less than a predetermined core flow to prevent the core from entering an unstable region of operation.

    摘要翻译： 本发明涉及用于保护诸如沸水反应堆堆芯的核反应堆堆芯免受由于在延长的工作潮流条件下的热水力不稳定性引起的燃料和包壳损坏的方法，并且特别是当实施延长的功率升高时。 这些方法采用现有许可的稳定性方法并且并入例如基于平均功率范围监视器（APRM）的跳闸系统的微小变化，以排除在功率/流量图的稳定性脆弱区域内的操作。 当核心流量小于预定的核心流量时，基于APRM的行程系统被修改以设置APRM流偏置scram线路，以防止核心进入不稳定的操作区域。

    DEVICE AND METHOD FOR FIXING REACTOR METERING PIPE
    6.
    发明公开
    DEVICE AND METHOD FOR FIXING REACTOR METERING PIPE 有权
    VORRICHTUNG UND VERFAHREN ZUR BEFESTIGUNG VON EINEM REAKTORMESSROHR

    公开(公告)号：EP3002762A1

    公开(公告)日：2016-04-06

    申请号：EP15195579.6

    申请日：2008-07-04

    申请人： Kabushiki Kaisha Toshiba

    发明人： Maehara, Takeshi ,  Iwasa, Hideshi ,  Watanabe, Yuusuke ,  Kinugasa, Kunihiko ,  Mori, Hajime ,  Saiki, Kiyofumi ,  Okuda, Ken ,  Hagiwara, Tsuyoshi ,  Saito, Noboru ,  Watanabe, Masanobu ,  Kasai, Shigeru

    IPC分类号： G21C13/032 ,  G21C15/25 ,  G21C17/032 ,  F16L3/02

    CPC分类号： G21C13/032 ,  F16L3/02 ,  G21C15/25 ,  G21C17/032 ,  G21Y2002/303 ,  G21Y2004/301 ,  Y02E30/40

    摘要： A reactor metering pipe fixing device fixes a reactor metering pipe disposed in a reactor to a cylindrical outer surface of a jet pump diffuser and reduces stress that may be induced in a weld zone in the reactor metering pipe. An outer holding member 41 is held on the cylindrical outer surface 18a of a jet pump diffuser 18 by a C-shaped holding member 30. The reactor metering pipe 19 is clamped from radial directions by the outer holding member 41 and inner holding members 42 and 43. Wedges 44 and 45 are wedged into a gap between the cylindrical outer surface 18a and the inner holding member 42 and a gap between the cylindrical outer surface 18a and the inner holding member 43 to fix the reactor metering pipe 19 firmly to the cylindrical outer surface 18a.

    摘要翻译： 反应器计量管固定装置将设置在反应器中的反应器计量管固定到喷射泵扩散器的圆柱形外表面，并减少可能在反应器计量管中的焊接区域中引起的应力。 外保持构件41通过C形保持构件30保持在喷射泵扩散器18的圆筒形外表面18a上。反应器计量管19通过外保持构件41和内保持构件42沿径向夹紧， 楔形件44和45楔入圆柱形外表面18a和内保持构件42之间的间隙以及圆柱形外表面18a和内保持构件43之间的间隙，以将反应器计量管19牢固地固定到圆柱形外 表面18a。

    ULTRASCHALLSENSOR ZUR MESSUNG VON STRÖMUNGSGESCHWINDIGKEITEN IN FLÜSSIGEN SCHMELZEN
    7.
    发明公开
    ULTRASCHALLSENSOR ZUR MESSUNG VON STRÖMUNGSGESCHWINDIGKEITEN IN FLÜSSIGEN SCHMELZEN 有权
    ULTRASCHALLSENSOR ZUR MESSUNG VONSTRÖMUNGSGESCHWINDIGKEITEN在FLÜSSIGENSCHMELZEN

    公开(公告)号：EP2158456A2

    公开(公告)日：2010-03-03

    申请号：EP08760778.4

    申请日：2008-06-10

    申请人： Forschungszentrum Dresden - Rossendorf e.V.

    发明人： ECKERT, Sven ,  GERBETH, Gunter ,  GUNDRUM, Thomas

    IPC分类号： G01F1/66 ,  G01F15/00 ,  G01F15/14 ,  G10K11/24 ,  G21C17/032

    CPC分类号： G01F1/662 ,  G01F15/006 ,  G01F15/14 ,  G10K11/24

    摘要： The invention relates to an ultrasonic sensor for measuring flow rates in liquid melts at high temperatures. The aim of the invention is to provide an ultrasonic sensor for carrying out local, continuous, reliable rate measurements in hot melts (T > 200°C). To achieve this, the ultrasonic sensor contains an ultrasonic waveguide (2) that is connected to the piezoelectric transducer (1) and consists of a material with low acoustic damping properties in a temperature range relevant for the area of application of above 200 °C, said material being chemically resistant to the melt. In addition, the end face of the ultrasonic waveguide (2) facing the melt is closed and can be wetted by the melt.

    摘要翻译： 本发明涉及一种用于测量高温液体熔体流速的超声波传感器。 本发明的目的是提供一种用于在热熔体中进行局部，连续，可靠的速率测量的超声波传感器。 为了实现这一点，超声波传感器包含连接到压电换能器的超声波波导，并且在与200℃以上的应用范围相关的温度范围内由具有低声阻尼特性的材料组成，所述材料耐化学性 熔化。 此外，面向熔体的超声波导管的端面被封闭，并且可以被熔体润湿。

    BWR core flow measurement
    9.
    发明公开
    BWR core flow measurement 失效
    BWR核心流量测量

    公开(公告)号：EP0380280A3

    公开(公告)日：1990-09-05

    申请号：EP90300656.7

    申请日：1990-01-22

    申请人： GENERAL ELECTRIC COMPANY

    发明人： O'Neil, Timothy Joseph ,  McGrady, Joseph Alva

    IPC分类号： G21C17/032

    CPC分类号： G21C17/032

    摘要： A boiling water reactor includes a pressure vessel having internal forced circulation through the core. An annular downcomer region establishes reactor coolant flow downwardly in the periphery of the reactor vessel and finally upwardly and centrally into the core across a core plate (30). A pressure sensor (32,34) detecting the pressure differential across the core plate is utilized. This pressure sensor has its measurement enhanced by input from local power range monitors (42,44,46,48,50,53,54,56) in the core to utilize both the sensed pressure differential and the power to predict more accurately flow in the reactor. An algorithm utilizes the pressure differential and the real time readings from the local power range monitor to accurately gauge overall reactor coolant flow. To ensure accurate calibration, two calibration standards are utilized at steady states of reactor power output and coolant flow. A first calibration standard includes the installation of thermocouples adjacent the reactor core plate for measurement of fluid enthalpy of the coolant as it flows upwardly through the reactor core. The determined enthalpy is utilized in an energy flow balance wherein the core flow rate is solved for as an unknown. A second calibration standard utilizes the sensed pressure differential across the annular pump deck of the forced circulation pumps. The two standards are combined in output utilizing a least squares averaging, and the result combined to calibrate the algorithm.