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
    • 22. 发明授权
    • Xenon oscillation prediction method and computer program for xenon oscillation prediction
    • 氙振荡预测方法和氙振荡预测计算机程序
    • US08792604B2
    • 2014-07-29
    • US12595744
    • 2008-04-30
    • Yoichiro Shimazu
    • Yoichiro Shimazu
    • G21C7/36G21C7/00
    • G21C7/00G21C7/005G21C17/00G21D3/001G21D3/04G21Y2002/201G21Y2004/40Y02E30/39
    • To predict xenon oscillation at the present time and later. For this purpose, as an axial offset of a power distribution of a reactor is represented by AOp, an axial offset of a power distribution based on xenon distribution is represented by AOx, and an axial offset of a power distribution based on an iodine distribution is represented by AOi, a parameter DAOpx(=AOp−AOx) and a parameter DAOix(=AOi−AOx) are described by a relational expression of a trigonometric function and an exponential function using an angular frequency of xenon oscillation. Next, phases with respect to initial values of the parameters DAOpx and DAOix are obtained (Step S101). The parameter DAOpx and the parameter DAOix expressed by the obtained phase and a coefficient of the relational expression obtained from this phase are plotted on an X coordinate and a Y coordinate, respectively. A locus at the present time and later is predicted using the locus obtained in this manner (Step S102), and a timing of extinguishing the xenon oscillation is predicted (Step S103).
    • 预测氙气振荡现在和以后。 为此,由于AOp表示反应堆功率分布的轴向偏移,所以基于氙分布的功率分布的轴向偏移由AOx表示,基于碘分布的功率分布的轴向偏移为 由AOi表示,参数DAOpx(= AOp-AOx)和参数DAOix(= AOi-AOx)通过使用氙振荡的角频率的三角函数和指数函数的关系表达式来描述。 接下来,获得关于参数DAOpx和DAOix的初始值的相位(步骤S101)。 通过获得的相位表示的参数DAOpx和参数DAOix以及从该相位获得的关系表达式的系数分别绘制在X坐标和Y坐标上。 使用以这种方式获得的轨迹预测当前时间和之后的轨迹(步骤S102),并且预测氙振荡的熄灭时间(步骤S103)。
    • 25. 发明申请
    • AUTOMATED TEST SYSTEM
    • 自动测试系统
    • US20140032158A1
    • 2014-01-30
    • US13560768
    • 2012-07-27
    • Hengyi Liang
    • Hengyi Liang
    • G06F19/00
    • G21C17/00G05B23/0256G21D3/001Y02E30/39
    • Systems and methods for automated testing of a distributed control system are provided. The automated test system includes a master station having a processing unit operably coupled to a user interface and a master wireless unit; and at least one remote station. Each remote station includes at least one output module to send outputs to a unit under test, at least one input module to receive inputs from the unit under test and a remote wireless unit operably coupled to the at least one output module and the at least one input module. The master station is configured to transmit outputs to the remote station by wireless communication and to receive inputs from the remote station by wireless communication. The received inputs are representative of a condition of the unit under test.
    • 提供了一种用于分布式控制系统自动化测试的系统和方法。 该自动化测试系统包括具有可操作地耦合到用户接口和主无线单元的处理单元的主站; 和至少一个远程站。 每个远程站包括至少一个输出模块,用于向被测单元发送输出,至少一个输入模块,用于接收来自被测单元的输入;以及远程无线单元,其可操作地耦合到所述至少一个输出模块和所述至少一个 输入模块 主站被配置为通过无线通信向远程站发送输出,并通过无线通信从远程站接收输入。 所接收的输入代表被测单元的状态。
    • 27. 发明申请
    • IN-SITU AND EXTERNAL NUCLEAR REACTOR SEVERE ACCIDENT TEMPERATURE AND WATER LEVEL PROBES
    • 现场和外部核反应堆严重意外温度和水位问题
    • US20130272468A1
    • 2013-10-17
    • US13444535
    • 2012-04-11
    • Eric P. LoewenBrian S. TriplettBrett J. Dooies
    • Eric P. LoewenBrian S. TriplettBrett J. Dooies
    • G21C17/00
    • G21C17/00G21C17/10G21D1/00G21D3/001Y02E30/40
    • A system for monitoring a state of a reactor core in a nuclear reactor may include an internal monitoring device located inside the reactor core, the internal monitoring device including one or more internal sensor arrays configured to take measurements of conditions of the reactor core at different vertical regions within the reactor core to generate internal measurement data; an external monitoring device located in the reactor structure outside the reactor core, the external monitoring device including one or more external sensor arrays configured to take measurements of conditions of the reactor core at positions outside the reactor core corresponding the plurality of different vertical regions within the reactor core to generate external measurement data, and a transmitter configured to wirelessly transmit the external measurement data; and a receiver station configured to determine a state of the reactor core based on the external and internal measurement data.
    • 用于监测核反应堆中的反应堆核心的状态的系统可以包括位于反应堆堆芯内部的内部监测装置,内部监测装置包括一个或多个内部传感器阵列,其被配置成在不同垂直方向上测量反应堆堆芯的状况 反应堆堆芯内的区域产生内部测量数据; 位于反应堆堆芯外部的反应堆结构中的外部监测装置,所述外部监测装置包括一个或多个外部传感器阵列,所述外部传感器阵列被配置为在所述反应堆堆芯外的位置处对应于所述反应堆堆芯内的所述多个不同垂直区域的位置 反应堆核心以产生外部测量数据;以及发射机,被配置为无线地传送外部测量数据; 以及接收站,被配置为基于所述外部和内部测量数据来确定所述电抗器堆芯的状态。
    • 29. 发明授权
    • Doppler reactivity coefficient measuring method
    • 多普勒反应性系数测定方法
    • US08462909B2
    • 2013-06-11
    • US12694729
    • 2010-01-27
    • Masatoshi YamasakiYasushi HanayamaYasunori OhokaMasashi TsujiYoichiro Shimazu
    • Masatoshi YamasakiYasushi HanayamaYasunori OhokaMasashi TsujiYoichiro Shimazu
    • G21C17/00
    • G21C17/104G21D3/001
    • 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.
    • 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 。