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RCIC TURBO-PUMP SCALING THROUGH CFD AND MODEL TESTING FOR THE TEXAS AM UNIVERSITY NHTS FACILITY

机译:德州农工大学NHTS设施通过CFD进行的RCIC涡轮定标和模型测试

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One of the requirements for licensing a nuclear power plant in the U.S is the capability to survive and recover from a station blackout according to the U.S Nuclear Regulatory Commission (USNRC). Station blackout is the loss of all off-site and onsite power simultaneously. Therefore, experimental test facilities are being constructed and operated to test the performance of the related safety systems in a nuclear power plant. Design and construction of a test facility creates the need to perform scaling analysis to ensure proper representation of key components and phenomena of interest. One of the main outcomes of the scaling analysis is the quantitative estimation of the Similarity Level (SL), which requires derivation of dimensionless scaling parameters and prediction of appropriate input values for the scaling parameters. To study the performance of the Reactor Core Isolation Cooling (RCIC) system, the Nuclear Heat Transfer Systems (NHTS) Laboratory at Texas A&M University has constructed and is operating a RCIC test facility. This paper presents the scaling analysis with reference to a full-size RCIC system and the RCIC system turbine was used as the main component for scaling. The input parameters for dimensionless scaling parameters were obtained through experimental measurements and CFD analysis. The CFD analysis is for the ZS-1 RCIC system turbine model. The STAR-CCM+ CFD code was used in this study to create and run simulations for steady state normal and abnormal operating conditions for the NHTS-developed CAD models. The input for the dimensionless scaling parameters was estimated. Input parameters were collected both experimentally and from CFD simulations and inserted into these equations. As a result, a high degree of similarity was confirmed, with a minimum of 82% between the NHTS and full-size RCIC systems. The 82% represents the amount of transfer properties conserved between the two systems. Consequently, this high similarity level allows the NHTS RCIC system to be used to study the behavior of the full-size RCIC system under Beyond Design Bases Accident (BDBA) conditions. Future work is to study and model other components of the RCIC system such as the suppression chamber to estimate similarity levels and study their effects on behavior of the system under BDBA.
机译:根据美国核监管委员会(USNRC)的规定,在美国核电站获得许可的要求之一是能够从停电中幸存和恢复。车站停电是同时失去所有场外和场内电力的原因。因此,正在建造和运行实验测试设施以测试核电厂中相关安全系统的性能。测试设施的设计和建造需要执行缩放分析,以确保正确表示关键组件和感兴趣的现象。缩放分析的主要结果之一是对相似度(SL)的定量估计,这需要推导无量纲缩放参数并预测缩放参数的适当输入值。为了研究反应堆堆芯隔离冷却(RCIC)系统的性能,德克萨斯A&M大学的核传热系统(NHTS)实验室已建成并正在运行RCIC测试设施。本文介绍了参考全尺寸RCIC系统进行的结垢分析,并且使用RCIC系统涡轮机作为结垢的主要组件。通过实验测量和CFD分析获得了无量纲缩放参数的输入参数。 CFD分析适用于ZS-1 RCIC系统涡轮机模型。这项研究中使用STAR-CCM + CFD代码为NHTS开发的CAD模型创建并运行稳态,正常和异常运行条件的仿真。估计了无量纲缩放参数的输入。通过实验和CFD模拟收集输入参数,并将其插入这些方程式。结果,证实了高度相似性,NHTS与全尺寸RCIC系统之间的相似度至少为82%。 82%表示两个系统之间保留的转移性质的数量。因此,这种高相似性水平使NHTS RCIC系统可用于研究超出设计基准事故(BDBA)情况下的全尺寸RCIC系统的行为。未来的工作是研究和建模RCIC系统的其他组件,例如抑制室,以估计相似性水平,并研究其对BDBA下系统行为的影响。

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