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    • 3. 发明授权
    • Portable object reader terminal, portable object, and process for self-diagnosis and supervision of same
    • 便携式对象阅读器终端,便携式对象,以及自我诊断和监督过程
    • US06505144B2
    • 2003-01-07
    • US09827905
    • 2001-04-09
    • Ronan Lapie
    • Ronan Lapie
    • G21C1700
    • G07F7/1008G06Q20/341G06Q20/3552G07F7/084
    • Terminal equipped with an application program, with at least one output constituted either by a display, or by a printer, or by a communications network, or by a portable object, and cooperating with a portable object equipped with a non-volatile memory area (ZD) containing data, and comprising a reader which communicates with said portable object, characterized in that the device comprises means for reading or storing, in its memory, self-diagnostic or supervisory data (Ti, Dj, Sk) and means for sending said data to outputs (1-4) specified as a function of information supplied by the self-diagnostic or supervisory data following the execution of at least one task Tt of its application program in connection with the portable object.
    • 具有应用程序的终端,至少一个输出由显示器,打印机,通信网络或便携式对象构成,并与配备有非易失性存储区域的便携式对象配合 ZD),并且包括与所述便携式对象通信的读取器,其特征在于,所述设备包括用于在其存储器中读取或存储自诊断或监视数据(Ti,Dj,Sk)的装置,以及用于发送所述 数据输出到输出(1-4),其被指定为在与便携式对象相关联的其应用程序的至少一个任务Tt的执行之后由自诊断或监督数据提供的信息的函数。
    • 4. 发明授权
    • In-core fixed nuclear instrumentation system and power distribution monitoring system
    • 核心固定核仪表系统和配电监控系统
    • US06408041B2
    • 2002-06-18
    • US09876029
    • 2001-06-08
    • Koji Hirukawa
    • Koji Hirukawa
    • G21C1700
    • G21C17/108
    • In an in-core fixed nuclear instrumentation system for a reactor, each of a plurality of in-core nuclear instrumentation assemblies has a nuclear instrumentation tube. LPRM detectors are housed in the nuclear instrumentation tube for detecting LPRM signal in a core of the reactor. A GT assembly is housed in the tube. The GT assembly has fixed GT detectors for detecting &ggr;-ray heating values and a built-in heater therein for calibrating the fixed GT detectors. The fixed GT detectors are arranged at least close to the fixed LPRM detectors, respectively. GT signals by the detected &ggr;-ray heating values of the fixed GT detectors of each GT assemblies are processed by a GT signal processing unit. The heater in each GT assemblies is electrically energized by a GT heater control unit. Predetermined time intervals are stored in a memory unit. One of the predetermined time intervals for specified &ggr;-ray thermometer assemblies, respectively is selected so that the GT heater control unit controls an electrical energy supplied to the heater by the selected interval so as to heat the heater, thereby executing a heater calibration of output voltage sensitivities of the fixed GT detectors of the GT assembly.
    • 在用于反应堆的核心固定核仪表系统中,多个核心核仪表组件中的每一个具有核仪器管。 LPRM探测器安装在核仪表管中,用于检测反应堆核心中的LPRM信号。 GT组件安装在管中。 GT组件具有用于检测伽马射线加热值的固定GT检测器和用于校准固定GT检测器的内置加热器。 固定的GT检测器分别至少靠近固定的LPRM探测器。 通过GT信号处理单元处理每个GT组件的固定GT检测器的检测伽马射线加热值的GT信号。 每个GT组件中的加热器由GT加热器控制单元供电。 预定时间间隔存储在存储器单元中。 分别选择指定的伽马射线温度计组件的预定时间间隔之一,使得GT加热器控制单元以供选择的间隔来控制供给加热器的电能,以加热加热器,由此执行加热器校准输出 GT组件的固定GT检测器的电压灵敏度。
    • 5. 发明授权
    • Portable object reader terminal and process for self-diagnosis and supervision of same
    • 便携式对象阅读器终端和过程自我诊断和监督
    • US06253163B1
    • 2001-06-26
    • US09125714
    • 1998-08-24
    • Ronan Lapie
    • Ronan Lapie
    • G21C1700
    • G07F7/1008G06Q20/341G06Q20/3552G07F7/084
    • A terminal includes a memory in which is stored an application program and further includes at least one output constituted either by a display, or by a printer, or by a communications network, or by a portable object. The terminal cooperates with a portable object such as a “smart card”, which includes a non-volatile memory area (ZD) containing data. The terminal includes a reader which communicates with the portable object and is characterized in that there is provided a mechanism for reading or storing self-diagnostic or supervisory data (Ti, Dj, Sk) in the terminal memory and a mechanism for sending the data to outputs (1-4) of the terminal specified as a function of information supplied by the self-diagnostic or supervisory data following the execution of at least one task Tt of the application program operating in connection with the portable object.
    • 终端包括存储应用程序的存储器,并且还包括由显示器,打印机,通信网络或便携式对象构成的至少一个输出。 终端与诸如“智能卡”的便携式对象协作,其包括包含数据的非易失性存储区域(ZD)。 终端包括与便携式对象进行通信的读取器,其特征在于,提供了一种用于在终端存储器中读取或存储自诊断或监视数据(Ti,Dj,Sk)的机制,以及用于将数据发送到 在执行与便携式对象相关联的应用程序的至少一个任务Tt的执行之后,由终端指定的终端的输出(1-4)作为由自诊断或监督数据提供的信息的函数。
    • 8. 发明授权
    • Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods
    • 用于产生核燃料棒运行的热机械极限的方法和系统
    • US06535568B1
    • 2003-03-18
    • US09678665
    • 2000-10-04
    • Anthony P. Reese
    • Anthony P. Reese
    • G21C1700
    • G21D3/001G21Y2002/201G21Y2004/40Y02E30/40
    • A method and system for demonstrating compliance of nuclear fuel rods with fundamental licensing criteria for fuel rod internal pressure during nuclear reactor operation is presented. A nuclear fuel rod evaluation process is performed during the fuel cycle design and licensing process for each operating cycle of a particular nuclear reactor. The evaluation process includes a rod-by-rod internal pressure analysis based on empirical data of actual operational power output levels of each fuel rod in the reactor core. A computer program constructs individual fuel rod power histories for each nuclear fuel rod in the reactor core based on empirical information acquired during previous fuel cycles and the projected operation of the reactor in an upcoming fuel cycle. Using the constructed power histories for each fuel rod, the program then computes thermal and mechanical overpower limits and a maximum internal pressure for each rod in the upcoming fuel cycle. Licensing compliance is demonstrated by confirming that the computed maximum internal pressure and maximum thermal and mechanical overpower stresses of any fuel rod for the upcoming fuel cycle is less than the fundamental licensing limits.
    • 介绍了核反应堆运行期间核燃料棒符合燃料棒内压基本许可标准的方法和系统。 在特定核反应堆的每个操作循环的燃料循环设计和许可过程中执行核燃料棒评估过程。 评估过程包括基于反应堆堆芯中每个燃料棒的实际操作功率输出水平的经验数据的逐棒内压分析。 计算机程序基于在先前燃料循环期间获取的经验信息以及反应堆在即将到来的燃料循环中的预计运行来为反应堆堆芯中的每个核燃料棒构建单独的燃料棒功率历史。 使用每个燃料棒构建的电力历史,程序然后计算即将到来的燃料循环中每个杆的热和机械过功率极限和最大内部压力。 通过确认任何燃料棒的即将到来的燃料循环的计算的最大内部压力和最大热力和机械过功率应力小于基本许可限制来证明许可合规性。