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首页> 外文会议>2002 ASME Pressure Vessels and Piping Conference, Aug 5-9, 2002, Vancouver, British Columbia, Canada >REACTOR PRESSURE VESSEL LIFE MANAGEMENT AT FRENCH PWR PLANTS
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REACTOR PRESSURE VESSEL LIFE MANAGEMENT AT FRENCH PWR PLANTS

机译：法国压水厂的反应堆压力容器寿命管理

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The capability of nuclear electricity generation by French Utility's EDF (Electricite de France) is 75% of global generation, 58 PWR units are in operation, 34 units three-loop, 20 units four-loop (1300MWe) and 4 units four-loop (1450MWe). The French Utility methodology to justified reactor vessel assessment on specific plants is to verify, for a known defect (real or hypothetic), safety margin to non ductile failure for each transient and for case of loading. The demonstration must be done for each instant of the reactor vessel life, and must include material embrittlement caused by irradiation degradation. This paper will describe EDF methodology aging assessment for at least 40 years, comparing: 1. The boundary RT_(NDT) (Reference Nil Ductility Transition Temperature) support by reactor vessel, 2. The estimated RT_(NDT) at 40 years. Estimated RT_(NDT) for 40 years is determined with a prediction formula that needs following input parameters: 1. The initial RTNDT during the construction, 2. Fluence assessment received by reactor vessel during 40 years in operation, 3. Chemistry material composition. The Boundary RT_(NDT) supported by reactor vessel is determined with a mechanical analysis that needs the following input parameters: 1. Defect characteristics 2. Transient definition The determination of each parameter will be described, and an experimental program to verify the conservatism of methodology will be presented (Irradiation Surveillance Programme).
机译：法国电力公司的EDF（Electricite de France）的核电发电能力占全球发电量的75％，正在运行58台PWR机组，三回路34台机组，四回路（1300MWe）20台机组，四回路（4台机组） 1450MWe）。法国公用事业公司对特定工厂进行反应堆容器评估合理性的方法是，针对已知缺陷（真实或假设），验证每次瞬变和负载情况下非延性失效的安全裕度。必须在反应堆容器寿命的每个瞬间进行演示，并且必须包括由辐照降解引起的材料脆化。本文将描述EDF方法至少40年的老化评估，并进行比较：1.反应堆容器的边界RT_（NDT）（参考零延性转变温度）支持； 2。40年的估计RT_（NDT）。使用需要以下输入参数的预测公式来确定40年的RT_（NDT）估算值：1.施工期间的初始RTNDT； 2。运行40年的反应堆容器收到的注量评估； 3。化学材料成分。通过机械分析确定反应堆容器支撑的边界RT_（NDT），该分析需要以下输入参数：1.缺陷特征2.瞬态定义将描述每个参数的确定，并通过实验程序验证方法学的保守性将被介绍（辐照监测计划）。

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