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公开(公告)号：US06799124B2
公开(公告)日：2004-09-28
申请号：US10011454
申请日：2001-11-29
IPC分类号： G01B344
CPC分类号： G06Q10/06
摘要： A probabilistic method for optimizing the inspection of a heat exchanger that determines the maximum number of degraded tubes that can be permitted to remain in service for a contemplated interval of time without exceeding an allowable probability of a tube burst, based upon Extreme Value Probability Distribution theory. The method also determines the minimum number of tubes that need to be inspected to establish that no more than the determined maximum number of degraded tubes will be permitted to remain in service for the contemplated interval of time based upon Bayesian Acceptance Sampling Theory.
摘要翻译： 一种概率方法，用于优化热交换器的检查，该热交换器基于极值概率分布理论，确定可以允许在预定的时间间隔内保持使用的劣化管的最大数量，而不超过管爆裂的容许概率。 。 该方法还确定需要检查的管的最小数目，以确定不超过所确定的降解管的最大数量将被允许在基于贝叶斯验收采样理论的预期时间间隔内保持服务。
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公开(公告)号：US4801421A
公开(公告)日：1989-01-31
申请号：US26501
申请日：1987-03-16
IPC分类号： G21C17/003 , G21C13/08 , G21C17/00 , G21C17/108
CPC分类号： G21C13/08 , G21C17/00 , G21C17/108 , Y02E30/40
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, RT.sub.ndt, required for flaw initiation and the actual RT.sub.ndt through the entire depth of the vessel wall at selected critical locations. When flaw initiation is indicated at any depth, the RT.sub.ndt 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.
摘要翻译： 核反应堆容器完整性的实时分析是通过监测反应堆冷却剂温度和压力以及快中子通量来实现的，并通过对其产生缺陷引发所需的参考无延展转变温度RTndt和通过实际RTndt进行视觉比较 在选定的关键位置的血管壁的整个深度。 当在任何深度指示缺陷开始时，也产生并显示缺陷传播停止所需的RTndt。 还可以生成显示器，以提供在加热和冷却期间的最佳性能的指导。 位于反应堆核心入口处的热电偶与冷腿管道中通常设置的电阻温度检测器RTD结合使用，以在容器中的关键位置产生更准确的冷却剂温度测量。 在停滞的流动条件下，将相关性应用于RTD读数，以提供关键位置的冷却剂温度的最佳估计。
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