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首页> 外文期刊>Nuclear Engineering and Design >Benchmark and parametric study of a passive flow controller (fluidic device) for the development of optimal designs using a CFD code
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Benchmark and parametric study of a passive flow controller (fluidic device) for the development of optimal designs using a CFD code

机译:使用CFD代码开发最优设计的无源流量控制器(流体设备)的基准和参数研究

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摘要

A passive flow controller or a fluidic device (FD) is used for a safety injection system (SIS) for efficient use of nuclear reactor emergency cooling water since it can control the injection flow rate in a passive and optimal way. The performance of the FD is represented by pressure loss coefficient (K-factor) which is further affected by the configuration of the components such as a control port direction and a nozzle angle. The flow control mechanism that is varied according to the water level inside a vortex chamber determines the duration of the safety injection.rnThis paper deals with a computational fluid dynamics (CFD) analysis for simulating the flow characteristics of the FD using the ANSYS CFX 11.0. The CFD analysis is benchmarked against existing experimental data to obtain applicability to the prediction of the FD performance in terms of K-factor. The CFD calculation is implemented with Shear Stress Transport (SST) model for a swirling flow and a strong streamline curvature in the vortex chamber of the FD, considering a numerical efficiency.rnBased on the benchmark results, parametric analyses are performed for an optimal design of the FD by varying the control port direction and the nozzle angle. Consequently, the FD performance is enhanced according to the angle of the control port nozzle.
机译:无源流量控制器或流体装置(FD)用于安全注入系统(SIS),以有效利用核反应堆应急冷却水,因为它可以以无源和最佳方式控制注入流量。 FD的性能由压力损失系数(K因子)表示,压力损失系数(K因子)进一步受到诸如控制端口方向和喷嘴角度等组件的配置的影响。根据涡流室内的水位而变化的流量控制机制决定了安全注入的持续时间。rn本文使用ANSYS CFX 11.0进行了计算流体动力学(CFD)分析,以模拟FD的流动特性。 CFD分析以现有的实验数据为基准,以获得适用于K因子的FD性能预测的适用性。考虑到数值效率,使用剪切应力传输(SST)模型对FD的涡流室中的旋流和强流线曲率进行CFD计算,考虑到数值效率.rn基于基准结果,进行参数分析以优化设计通过更改控制端口方向和喷嘴角度来确定FD。因此,根据控制端口喷嘴的角度,可以提高FD性能。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2010年第5期|p.1139-1150|共12页
  • 作者单位

    NSSS Design & Development team, Advanced Plant Development Office, Nuclear Engineering & Technology Institute, Korea Hydro & Nuclear Power Company, Ltd., 508 Kumbyungro, Yuseong-gu, Daejeon 305-343, Republic of Korea;

    NSSS Design & Development team, Advanced Plant Development Office, Nuclear Engineering & Technology Institute, Korea Hydro & Nuclear Power Company, Ltd., 508 Kumbyungro, Yuseong-gu, Daejeon 305-343, Republic of Korea;

    NSSS Design & Development team, Advanced Plant Development Office, Nuclear Engineering & Technology Institute, Korea Hydro & Nuclear Power Company, Ltd., 508 Kumbyungro, Yuseong-gu, Daejeon 305-343, Republic of Korea;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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