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ON-LINE MONITOR AND ANALYZING METHOD OF PRESSURE VESSEL FOR NUCLEAR REACTOR

机译:核反应堆压力容器在线监测与分析方法

摘要

A real time analysis of nuclear reactor vessel integrity is preformed 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 locations. When flaw initiation is indicated at any depth, the RTndt required for flaw propagation arrest is also generated and displayed. A display can also be generated to provide guidance for optimum performance during heatup and cooldown. Thermocouples located at the reactor core inlet are used in conjunction with the resistance temperature detectors, RTDs, conventionally provided in the cold leg conduits to generate a more accurate measurement of the coolant temperature at the critical locations in the vessel. Under stagnant flow conditions a correlation is applied to the RTD readings to provide the best estimate of coolant temperature at the critical locations.
机译:通过监测反应堆冷却剂温度和压力以及快速中子注量,并由此生成缺陷引发所需的参考零延性转变温度RTndt和通过反应堆的实际RTndt的视觉比较,可以对核反应堆容器的完整性进行实时分析。在选定的关键位置处的整个壁厚。当在任何深度指示缺陷开始时,也会生成并显示缺陷传播阻止所需的RTndt。还可以生成显示以提供指导,以在加热和冷却期间获得最佳性能。位于反应堆堆芯入口处的热电偶与常规设置在冷段导管中的电阻温度检测器RTD结合使用,以在容器的关键位置生成更精确的冷却液温度测量值。在停滞的流量条件下,将相关性应用于RTD读数,以提供关键位置处冷却液温度的最佳估计值。

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