会员体验
专利管家(专利管理)
工作空间(专利管理)
风险监控(情报监控)
数据分析(专利分析)
侵权分析(诉讼无效)
联系我们
交流群
官方交流:
QQ群: 891211   
微信请扫码    >>>
现在联系顾问~
热词
    • 41. 发明授权
    • Incore monitoring method and incore monitoring equipment
    • 监控监控方式,监控设备
    • US06744840B2
    • 2004-06-01
    • US10256232
    • 2002-09-27
    • Yoshiji KarinoJun Hamada
    • Yoshiji KarinoJun Hamada
    • G21C1700
    • G21C17/108
    • An incore monitoring method of a nuclear reactor, includes, measuring neutron flux levels at pitch levels corresponding to local power range monitor sensors arranged along an axial direction inside a detector assembly installed in a nuclear reactor; performing power calculation, including calculation of thermal characteristics, of fuel assembly group consisting of fuel assemblies adjacent to the corresponding detector assembly, based on indicated values of the local power range monitor sensors of the corresponding detector assembly at a first time, calculating thermal characteristics at a second, subsequent time in which the power calculation is not calculated, based on values indicated by the local power range monitor sensors and calculated thermal characteristics at the first time and values indicated by the corresponding local power range monitor sensors at the second time, and monitoring the calculated thermal characteristics.
    • 核反应堆的不良监测方法包括:测量对应于安装在核反应堆中的检测器组件内沿轴向布置的局部功率范围监测传感器的间距级别的中子通量水平; 基于相应的检测器组件的局部功率范围监视传感器的指示值,在第一时间执行由与相应检测器组件相邻的燃料组件组成的燃料组件组的热特性的计算,计算热特性,计算热特性 基于由本地功率范围监视传感器指示的值和第一次计算的热特性以及第二次由相应的局部功率范围监视器传感器指示的值的第二次后续时间计算功率计算,以及 监测计算的热特性。
    • 46. 发明授权
    • Device for measuring the drop time of control rods into the core of a nuclear reactor
    • 用于测量控制棒进入核反应堆核心的下落时间的装置
    • US06606367B2
    • 2003-08-12
    • US09790649
    • 2001-02-23
    • Hervé HalluinPhilippe Paris
    • Hervé HalluinPhilippe Paris
    • G21C1700
    • G21C17/00G21Y2002/202G21Y2002/205G21Y2002/304G21Y2004/30G21Y2004/304
    • The measurement device comprises a real-time measurement-signal acquisition module (25) and means (23, 24) for connecting the cables for picking up the voltage from electrical windings for measuring the movement of the control rods to the acquisition module (25), in order to deliver, to the acquisition module (25), voltage signals corresponding to the voltage induced in the windings while the control rods are being dropped. The signal acquisition module (25) is thus permanently connected to the voltage-signal pickup cables (29) and the signals relating to the set of nuclear reactor control rods may be recorded simultaneously. Means (26, 27) for using the voltage signals delivered by the acquisition system (25) allow the drop times of the control rods to be determined.
    • 测量装置包括实时测量信号采集模块(25)和用于连接电缆的装置(23,24),用于从电气绕组拾取电压,用于测量控制棒到采集模块(25)的运动, ,以便在控制棒正在掉落的同时向采集模块(25)传送对应于绕组中感应的电压的电压信号。 因此,信号采集模块(25)永久地连接到电压信号拾取电缆(29),并且可以同时记录与该组核反应堆控制棒相关的信号。 用于使用由采集系统(25)传送的电压信号的装置(26,27)允许确定控制棒的下落时间。
    • 48. 发明授权
    • Method of calibrating exit thermocouples in a nuclear reactor
    • 在核反应堆中校准出口热电偶的方法
    • US06493412B1
    • 2002-12-10
    • US09686427
    • 2000-10-11
    • William A. BoydToshia MoritaDavid J. Krieg
    • William A. BoydToshia MoritaDavid J. Krieg
    • G21C1700
    • G21C17/112G21C17/022G21Y2002/204G21Y2004/401G21Y2004/402G21Y2004/403
    • The exit thermocouples of a pressurized water reactor (PWR) are calibrated by recording the thermocouple temperature measurements periodically during power ascension of the reactor together with a predicted power at the corresponding locations at the same time determined by a three-dimensional analytical nodal model of the core at the same core average power. The temperature measurements are converted to local core power values which are then divided into the corresponding predicted powers for the corresponding locations to arrive at mixing factors which are fitted to a selected function of core power. These mixing factors are recorded and subsequently applied to local power values calculated from measured exit thermocouple temperatures to adjust the three-dimensional nodal model power. Periodically, the mixing factors are adjusted by using flux map data to update the three-dimensional analytical nodal model power to generate a reference power distribution, calculating updated mixing factors using the current thermocouple temperature measurement taken at the same time and therefore the same average core power, and the reference power distribution, and then shifting the mixing factor functions of core power accordingly to pass through the updated mixing factors.
    • 压力水反应堆(PWR)的出口热电偶通过在反应堆的升压期间周期性地记录热电偶温度测量以及在相应位置处的预测功率同时由三维分析节点模型 核心在同等的核心平均功率。 将温度测量值转换为局部核心功率值,然后将其分为对应位置的相应预测功率,以得到拟合到所选核心功率功能的混合因子。 记录这些混合因子并随后应用于从测量的出口热电偶温度计算的局部功率值,以调整三维节点模型功率。 周期性地,通过使用通量图数据来调整混合因子,以更新三维分析节点模型功率以产生参考功率分布,使用同时进行的当前热电偶温度测量来计算更新的混合因子,因此相同的平均核心 功率和参考功率分配,然后相应地转移核心功率的混合因子功能以通过更新的混合因子。
    • 50. 发明授权
    • Monitoring control rod element assembly position
    • 监控杆元件装配位置
    • US06421405B1
    • 2002-07-16
    • US09819967
    • 2001-03-28
    • Charles F. Ridolfo
    • Charles F. Ridolfo
    • G21C1700
    • G21C17/12G21C7/36Y02E30/39
    • Compliance with administrative limits on cumulative exposure of control rod groups in the reactor core, is monitored by computing the incremental effective exposure for each group commensurate with core power, for each time increment at which each group is within the position range where an administrative limit is imposed. The increments of effective exposures for each group are accumulated, and the accumulated effective exposure for each group is compared with the administrative limit to each group. This comparison is then displayed to the reactor operator, preferably using either a “rolling wheel” or “sliding bar” format.
    • 通过计算与核心功率相称的每个组的增量有效暴露,对每个组在每个时间段内的行政限制在行政限制为 强加。 累计每组有效敞口增量,并将每组的累计有效风险与每组的行政限额进行比较。 然后将该比较显示给反应器操作者,优选使用“滚轮”或“滑动条”格式。