首页> 外国专利> METHOD AND ITS CORRESPONDING APPARATUS OF VERIFICATION AND ONLINE ANALYSIS OF INTEGRITY AGAINST NON-DUCTILE FAILURE OF THE PRESSURE CONTAINER WALL OF A NUCLEAR REACTOR.

METHOD AND ITS CORRESPONDING APPARATUS OF VERIFICATION AND ONLINE ANALYSIS OF INTEGRITY AGAINST NON-DUCTILE FAILURE OF THE PRESSURE CONTAINER WALL OF A NUCLEAR REACTOR.

机译:核反应堆压力容器壁非延性破坏的完整性验证和在线分析方法及其相应装置

摘要

A real time monitoring and analysis of nuclear reactor vessel integrity is performed by monitoring reactor coolant temperature and pressure and fast neutron fluence, and generating therefrom a visual comparison of the reference nil-ductility transition temperature, RTndt, required for flaw initiation and the actual RTndt through the entire depth of the vessel wall at selected critical points. The thermocouples disposed at the reactor core inlet and the resistance temperature detectors, RTDs, disposed at the cold leg conduits provide a measurement of the coolant temperature at the critical points of the vessel. Under stagnant flow conditions, empirically developed conversion factors are applied to the RTD and thermocouple readings to provide the best estimate of the coolant temperature at the critical points.
机译:实时监测和分析核反应堆容器的完整性是通过监测反应堆冷却剂的温度和压力以及中子的快速通量,并由此生成缺陷起始所需的参考零延性转变温度RTndt和实际RTndt的可视比较。在选定的临界点穿过血管壁的整个深度。布置在反应堆堆芯入口处的热电偶和布置在冷腿导管处的电阻温度检测器RTD提供对容器关键点处的冷却剂温度的测量。在流量停滞的情况下,将根据经验得出的转换系数应用于RTD和热电偶读数,以对临界点处的冷却液温度进行最佳估算。

著录项

  • 公开/公告号ES555672A0

    专利类型

  • 公开/公告日1988-02-16

    原文格式PDF

  • 申请/专利权人 WESTINGHOUSE ELECTRIC CORPORATION;

    申请/专利号ES19860555672

  • 发明设计人

    申请日1986-06-03

  • 分类号G21C17/10;

  • 国家 ES

  • 入库时间 2022-08-22 06:57:23

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