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FORTUM PARTICIPATION IN IAEA BENCHMARK FOR KKNPP7 RHR PIPING RESPONSE NCO 2007 EVENT

机译:KKNPP7 RHR管道响应NCO 2007事件参加国际原子能机构基准测试

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In this report Fortum participation in a benchmark related to the residual heat removal (RHR) piping system response of the Kashiwazaki-Kariwa Nuclear Power Plant unit 7 (KKNPP7) of Tokyo Electric Power Company (TEPCO) in Japan, during the 16 July 2007 Niigataken-Chuetsu-Oki earthquake (NCO) is described. The goal of this benchmark is to conduct a comparison between different analytical techniques, as used in die usual engineering practice.Equipment behavior during the NCO earthquake constitutes an extensive database. There are no direct acceleration or displacement measurements on equipment. For this reason quantitative simulation comparison is not possible. Qualitative observations of the fuel tank sloshing and tank buckling are available and these can be used in numerical simulation benchmark.The benchmark is divided in three phases and it will be carried out during the years of 2009-211. The number of participants in the benchmark is 25 organizations and institutions. Detailed goals of the benchmark as a whole can be summarized as follows:1) Understanding of soil, structures and mechanical equipment response during the Niigataken-Chuetsu-Oki earthquake.2) Simulation of equipment response for residual heat removal equipment.3) Simulation of liquid sloshing in the fuel pools in reactor building4) Simulation of buckling phenomena of vertical, . cylindrical yard tanksIn order to carry out this simulation task a joint model of the reactor building and the residual heat removal-system is developed.The main results of the numerical simulation will be the maximum values of the stresses in the most critical locations ofthe residual heat removal piping system. These values will be compared to known material properties of the piping such as yield and the tensile failure strain.
机译:在本报告中,Fortum参与了2007年7月16日日本东京电力公司(TEPCO)的柏崎崎-wa羽核电站7号机组(KKNPP7)的余热消除(RHR)管道系统响应相关的基准测试。 -描述了中越冲木地震(NCO)。该基准测试的目的是在通常的工程实践中使用的不同分析技术之间进行比较。 NCO地震期间的设备行为构成了一个广泛的数据库。设备上没有直接的加速度或位移测量值。因此,不可能进行定量模拟比较。可对油箱晃动和油箱屈曲进行定性观测,这些观测可用于数值模拟基准。 该基准分为三个阶段,将在2009-211年期间实施。基准测试的参与者有25个组织和机构。整个基准的详细目标可以总结如下: 1)理解新竹岳-中越-冲地震中的土壤,结构和机械设备的响应。 2)模拟设备对残留热量去除设备的响应。 3)模拟反应堆建筑物燃料池中的液体晃动 4)垂直屈曲现象的模拟。圆柱形堆场坦克 为了执行此模拟任务,开发了反应堆建筑物和余热去除系统的联合模型。 数值模拟的主要结果将是最关键位置的应力最大值。 余热排出管道系统。将这些值与管道的已知材料特性(例如屈服和拉伸破坏应变)进行比较。

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