公开(公告)号：US08489338B2

公开(公告)日：2013-07-16

申请号：US12521422

申请日：2007-12-21

申请人： Claude Verneret

发明人： Claude Verneret

IPC分类号： G01N31/00 ,  G21C17/00

CPC分类号： G21C17/022 ,  G21Y2002/204 ,  G21Y2004/40

摘要： In a process for estimating the concentration (C) of a chemical element in the primary coolant of a nuclear reactor, a dilution solution or a concentrated solution of said chemical element in a predetermined concentration (C*) is injected into the primary coolant within the reactor, and the reactor includes a sensor capable of measuring a quantity (Cm) representing the concentration of said chemical element. The process is an iterative process in which repeatedly in each time step k: a stage of acquiring quantities (qdk) and (qck) representing the injected flows of dilution solution and concentrated solution in step k, and a quantity (Cmk) representing the concentration measured by the sensor; a stage of calculating an estimated value (Cek+1) of the concentration of said chemical element in the primary coolant in step k+1 on the basis of representative quantities (qdk, qck, Cmk) acquired in stage k.

摘要翻译： 在用于估计核反应堆的一次冷却剂中的化学元素的浓度（C）的方法中，将预定浓度（C *）的所述化学元素的稀释溶液或浓缩溶液注入到 反应器，并且反应器包括能够测量表示所述化学元素的浓度的量（Cm）的传感器。 该过程是在每个时间步骤k中重复的迭代过程：在步骤k中获取表示稀释溶液和浓缩溶液的注入流量的量（qdk）和（qck）的阶段和表示浓度的量（Cmk） 由传感器测量; 基于在阶段k中获取的代表量（qdk，qck，Cmk）计算步骤k + 1中的一次冷却剂中的所述化学元素的浓度的估计值（Cek + 1）的阶段。

公开(公告)号：US08489209B2

公开(公告)日：2013-07-16

申请号：US13357413

申请日：2012-01-24

申请人： Kevin Dale Starr ,  Timothy Andrew Mast ,  Robert Trent Garverick

发明人： Kevin Dale Starr ,  Timothy Andrew Mast ,  Robert Trent Garverick

IPC分类号： G05B11/01 ,  G05B13/02 ,  G06F17/18 ,  G06F19/00 ,  G06F11/30 ,  G21C17/00 ,  H03F1/26 ,  H04B15/00

CPC分类号： G05B23/0216

摘要： A method is provided for analyzing and diagnosing a large scale process automation control system having a plurality of control loops. Assessments for pre-defined key performance indicators (KPIs) are automatically generated for control, process and signal sections of each control loop. The automatically generated assessments of the pre-defined KPIs may be displayed in a graphical user interface (GUI) of a computer. A user may change the automatically generated assessments of the pre-defined KPIs. Different data views may also be displayed in the GUI. The data views include time series trends for measured process variable, controller output, controller set point and error, as well as controller parameter clustering views in two-dimensional and three-dimensional plots.

摘要翻译： 提供了一种用于分析和诊断具有多个控制回路的大规模过程自动化控制系统的方法。 对每个控制回路的控制，过程和信号部分自动生成预定义的关键性能指标（KPI）的评估。 预定义的KPI的自动生成的评估可以显示在计算机的图形用户界面（GUI）中。 用户可以更改自动生成的预定义KPI评估。 GUI中也可能显示不同的数据视图。 数据视图包括测量过程变量，控制器输出，控制器设定点和误差以及二维和三维图中控制器参数聚类视图的时间序列趋势。

公开(公告)号：US08462909B2

公开(公告)日：2013-06-11

申请号：US12694729

申请日：2010-01-27

申请人： Masatoshi Yamasaki ,  Yasushi Hanayama ,  Yasunori Ohoka ,  Masashi Tsuji ,  Yoichiro Shimazu

发明人： Masatoshi Yamasaki ,  Yasushi Hanayama ,  Yasunori Ohoka ,  Masashi Tsuji ,  Yoichiro Shimazu

IPC分类号： G21C17/00

CPC分类号： G21C17/104 ,  G21D3/001

摘要： The output of a nuclear reactor is increased by a predetermined magnitude, and the neutron beam is measured as time-series data. The temperature of the moderator in the reactor is acquired as time-series data. Time-series data on the reactivity is acquired from the time-series data on the neutron beam by the reverse dynamic characteristic method with respect to a one-point reactor kinetics equation. Time-series data on the fuel temperature of a predetermined average acquired by using the time-series data on the reactor output and a predetermined dynamic characteristic model is acquired. The reactivity feedback contribution component is determined by using the time-series data on the reactivity and the applied reactivity. The Doppler reactivity coefficient is determined by using the time-series data on the average temperature of the moderator in the reactor, the time-series data on the fuel temperature of the predetermined average, the isothermal temperature reactivity coefficient, and the reactivity feedback contribution component.

摘要翻译： 核反应堆的输出增加了预定的大小，中子束被测量为时间序列数据。 反应器中的调节剂的温度作为时间序列数据获得。 关于反应性的时间序列数据通过反向动态特性方法相对于单点反应器动力学方程从中子束的时间序列数据获得。 获取通过使用反应堆输出上的时间序列数据获得的预定平均燃料温度的时间序列数据和预定的动态特性模型。 通过使用关于反应性和施加的反应性的时间序列数据来确定反应性反应贡献分量。 通过使用关于反应器中的缓和剂的平均温度的时间序列数据，预定平均值的燃料温度的时间序列数据，等温温度反应性系数和反应性反应贡献成分来确定多普勒反应性系数 。

公开(公告)号：US08451100B2

公开(公告)日：2013-05-28

申请号：US12578156

申请日：2009-10-13

申请人： Wolfgang Offermann ,  Martin Stephan

发明人： Wolfgang Offermann ,  Martin Stephan

IPC分类号： H04Q5/22 ,  G21C7/36 ,  G21C17/00

CPC分类号： G06K19/07749 ,  G06K19/07703

摘要： Described is the use of a transponder in a commercial installation, particularly a power plant, which allows problems and dangerous situations existing in this context to be avoided and the attainable occupational safety in a commercial installation, particularly a power plant, to be increased. The transponder includes a reception element, a transmission element, a visual display unit and a memory element and also a control element which is operatively connected to these, in a commercial installation, particularly a power plant, in an arrangement or positioning on or in proximity to a component or at a switching or measuring point associated with the component for the purpose of visually displaying an operating state for the component or the switching or measuring point associated therewith using the visual display unit of the transponder.

摘要翻译： 描述了在商业设施中，特别是电厂的应答器的使用，其允许避免在此上下文中存在的问题和危险情况，并且可以增加商业设施，特别是发电厂中可达到的职业安全性。 应答器包括接收元件，传输元件，视觉显示单元和存储器元件，以及控制元件，其可操作地连接到这些，在商业安装中，特别是电厂中，在或在其上或在其附近定位 到与组件相关联的组件或切换或测量点，以便使用应答器的可视显示单元可视地显示组件或与其相关联的切换或测量点的操作状态。

公开(公告)号：US20130121450A1

公开(公告)日：2013-05-16

申请号：US13672984

申请日：2012-11-09

申请人： Fujio SHIRAISHI ,  Hisayoshi FUKAI

发明人： Fujio SHIRAISHI ,  Hisayoshi FUKAI

IPC分类号： G21C17/00

CPC分类号： G21C17/00 ,  G21C15/182 ,  G21C17/02 ,  G21C17/035 ,  Y02E30/40

摘要： A water filling system for a reactor water level gauge is provided for filling a reactor water level gauge instrumentation pipe in a reactor building with water and filling the reactor water level gauge with water even in an unexpected abnormal event where the reactor building is brought into a highly radioactive environment. The water filling system for a reactor water level gauge includes a water filling instrumentation pipe guided from the reactor water level gauge instrumentation pipe in the reactor building to an outside of the reactor building and filling the reactor water level gauge instrumentation pipe in the reactor building with water even in an unexpected abnormal event of a nuclear power plant.

摘要翻译： 提供了一种用于反应堆水位计的充水系统，用于在具有水的反应堆建筑物中填充反应堆水位计仪表管，并且即使在意外的异常事件中将反应堆建筑物置于 高放射性环境。 反应堆水位计的注水系统包括从反应堆建筑物内的反应堆水位计仪表管引导到反应堆建筑物外部的充水仪表管道，并在反应堆建筑物内填充反应堆水位计仪表管道​​， 即使在核电厂意外的异常事件中也是如此。

公开(公告)号：US08438117B2

公开(公告)日：2013-05-07

申请号：US11314373

申请日：2005-12-20

申请人： Jean-Marc Berthaud ,  Melissa Buco ,  Rong N. Chang ,  Joel D. Dalsky ,  Shih-Chung Fang ,  Laura Zaihua Luan ,  Lee Tsiao ,  Christopher Ward

发明人： Jean-Marc Berthaud ,  Melissa Buco ,  Rong N. Chang ,  Joel D. Dalsky ,  Shih-Chung Fang ,  Laura Zaihua Luan ,  Lee Tsiao ,  Christopher Ward

IPC分类号： G06Q10/00 ,  G06F11/30 ,  G21C17/00

CPC分类号： H04L41/5019 ,  G06Q30/02

摘要： A method and system for managing a service level of a service provided by a service provider to a customer under a service level agreement. The actual measurement data is adjudicated to correct the measurement data in accordance with at least one adjudication element that provides information relating to how to correct the measurement data. The adjudicated measurement data is transformed into operational data by being reorganized into one or more groups of data. The operational data is evaluated by applying a formula to the operational data, resulting in the operational data being configured for being subsequently qualified. The operational data is qualified by comparing the evaluated operational data with specified service level targets for at least one service level period and identifying operational data points meeting and/or not meeting the specified service level targets.

摘要翻译： 一种用于根据服务级别协议来管理服务提供商向客户提供的服务的服务水平的方法和系统。 根据提供与如何校正测量数据有关的信息的至少一个判定元件，裁定实际测量数据来校正测量数据。 通过重新组织成一组或多组数据，将裁定的测量数据转换为操作数据。 通过对运行数据应用公式来评估运行数据，从而使运行数据配置为随后进行合格。 操作数据通过将评估的操作数据与至少一个服务级别周期的指定服务级别目标进行比较并识别会议和/或不符合指定的服务级别目标的操作数据点来限定。

公开(公告)号：US08437445B2

公开(公告)日：2013-05-07

申请号：US11503268

申请日：2006-08-14

申请人： David Galbally ,  Daniel Verne Sommerville ,  Matthew Christopher O'Connor ,  Daniel Charles Pappone ,  Hardayal Mehta ,  Leslie Wellstein

发明人： David Galbally ,  Daniel Verne Sommerville ,  Matthew Christopher O'Connor ,  Daniel Charles Pappone ,  Hardayal Mehta ,  Leslie Wellstein

IPC分类号： G21C17/00

CPC分类号： G21C17/00

摘要： A method of predicting stresses on a BWR steam dryer that includes creating an analytical acoustic model of a BWR steam system; generating pressure estimations by inputting empirical data into the analytical acoustic model of the BWR steam system; creating an analytical structural model of the BWR steam dryer; and predicting stresses on the BWR steam dryer using the analytical structural model and the pressure estimations.

摘要翻译： 一种在BWR蒸汽干燥机上预测应力的方法，包括创建BWR蒸汽系统的分析声学模型; 通过将经验数据输入到BWR蒸汽系统的分析声学模型中来产生压力估计; 创建BWR蒸汽干燥机的分析结构模型; 并使用分析结构模型和压力估计预测BWR蒸汽干燥器的应力。

公开(公告)号：US08406368B2

公开(公告)日：2013-03-26

申请号：US12595546

申请日：2008-04-11

申请人： Hironori Kumanomido ,  Naotaka Oda ,  Yutaka Tokiwa ,  Makoto Ueda

发明人： Hironori Kumanomido ,  Naotaka Oda ,  Yutaka Tokiwa ,  Makoto Ueda

IPC分类号： G21C17/10 ,  G21C17/108 ,  G21C17/00

CPC分类号： G21C17/063 ,  G21Y2002/201 ,  G21Y2002/204 ,  G21Y2004/30 ,  G21Y2004/40

摘要： An upper detector and a lower detector that face at least one side of a fuel assembly, on which neutrons are irradiated in a nuclear reactor, and detect radiation are set at a predetermined interval in an axial direction of the fuel assembly. Distributions of radiation signals are measured by the upper detector and the lower detector while the fuel assembly and the upper detector and the lower detectors are relatively moved along the axial direction of the fuel assembly. Soundness of radiation signals measured by the upper detector and the lower detector is determined in every measurement by comparing radiation signal distributions obtained by measuring the same portion in the axial direction of the fuel assembly in a multiplexed manner with the upper detector and the lower detector. Thereafter, relative burn-up is calculated by utilizing the measured radiation signals to measure a burn-up profile. According to the present invention, it is possible to measure a burn-up profile of the fuel assembly while securing reliability of a measurement result.

摘要翻译： 面向燃料组件的至少一侧的上检测器和下检测器，其中在核反应堆中辐射中子并检测辐射，沿燃料组件的轴向方向被设定为预定的间隔。 辐射信号的分布由上检测器和下检测器测量，而燃料组件和上检测器和下检测器沿着燃料组件的轴向方向相对移动。 通过比较通过以多路复用方式与上部检测器和下部检测器测量燃料组件的轴向方向上的相同部分而获得的辐射信号分布，在每次测量中确定由上部检测器和下部检测器测量的辐射信号的良好性。 此后，通过利用测量的辐射信号来计算相对燃耗以测量燃尽曲线。 根据本发明，可以在确保测量结果的可靠性的同时测量燃料组件的燃尽曲线。

公开(公告)号：US08401141B2

公开(公告)日：2013-03-19

申请号：US12345438

申请日：2008-12-29

申请人： Makoto Ueda ,  Hironori Kumanomido ,  Ishi Mitsuhashi ,  Tsukasa Kikuchi ,  Kenichi Yoshioka ,  Tomoharu Sasaki ,  Kouji Hiraiwa

发明人： Makoto Ueda ,  Hironori Kumanomido ,  Ishi Mitsuhashi ,  Tsukasa Kikuchi ,  Kenichi Yoshioka ,  Tomoharu Sasaki ,  Kouji Hiraiwa

IPC分类号： G21C17/00

CPC分类号： G21C1/084 ,  G21C17/10 ,  G21Y2002/201 ,  G21Y2002/204 ,  G21Y2002/304 ,  G21Y2004/40 ,  Y02E30/31

摘要： A first intensity Az expressed as Az=az×Eα, a first reference intensity A0 expressed as A0=a0×Eα, a second intensity Bz expressed as Bz=bz×E, and a second reference intensity B0=b0×E, are evaluated. The first intensity and the first reference intensity are of radioactive nuclides generated by a neutron capture reaction of a heavy nuclide or a fission product nuclide. The second intensity and the second reference intensity are of radioactive fission product nuclides except nuclides generated by a neutron capture reaction. The reference intensities are measured where the void fraction is known. Also a correlation curve of (az/a0) and a void fraction is evaluated. Finally an axial void fraction distribution is evaluated based on the value of (az/a0) and the correlation curve.

摘要翻译： 表示为Az = az×Eα的第一强度Az，表示为A0 = a0×Eα的第一参考强度A0，表示为Bz = bz×E的第二强度Bz和第二参考强度B0 = b0×E 。 第一强度和第一参考强度是由重核素或裂变产物核素的中子捕获反应产生的放射性核素。 第二强度和第二参考强度是放射性裂变产物核素，除了由中子俘获反应产生的核素外。 在已知空隙率的情况下测量参考强度。 还评估（az / a0）和空隙率的相关曲线。 最后，基于（az / a0）的值和相关曲线来评估轴向空隙率分布。

公开(公告)号：US08384004B1

公开(公告)日：2013-02-26

申请号：US12692323

申请日：2010-01-22

申请人： Mark S. Rowland ,  Raymond A. Alvarez

发明人： Mark S. Rowland ,  Raymond A. Alvarez

IPC分类号： G01T3/00 ,  G06M11/00 ,  G21C17/00

CPC分类号： G01T3/00 ,  H01J47/12

摘要： Embodiments are directed to a digital data acquisition method that collects data regarding nuclear fission at high rates and performs real-time preprocessing of large volumes of data into directly useable forms for use in a system that performs non-destructive assaying of nuclear material and assemblies for mass and multiplication of special nuclear material (SNM). Pulses from a multi-detector array are fed in parallel to individual inputs that are tied to individual bits in a digital word. Data is collected by loading a word at the individual bit level in parallel, to reduce the latency associated with current shift-register systems. The word is read at regular intervals, all bits simultaneously, with no manipulation. The word is passed to a number of storage locations for subsequent processing, thereby removing the front-end problem of pulse pileup. The word is used simultaneously in several internal processing schemes that assemble the data in a number of more directly useable forms. The detector includes a multi-mode counter that executes a number of different count algorithms in parallel to determine different attributes of the count data.

摘要翻译： 实施例涉及一种数字数据采集方法，其以高速率收集有关核裂变的数据，并将大量数据进行实时预处理，以直接使用形式，用于对核材料和组件执行无损检测的系统 特种核材料（SNM）的质量和倍增。 来自多检测器阵列的脉冲并行馈送到与数字字中的各个位相连的各个输入。 通过并行地在单个位电平上加载字来收集数据，以减少与当前移位寄存器系统相关联的延迟。 该字被定期读取，所有位同时进行，无需操作。 该字被传递到多个存储位置用于后续处理，从而消除了脉冲堆积的前端问题。 这个词在几个内部处理方案中同时使用，它们以多种更直接可用的形式组合数据。 检测器包括并行执行多个不同计数算法的多模式计数器，以确定计数数据的不同属性。