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Development and application of an efficient method for performing modal analysis of steam generator tubes in nuclear power plants

机译:核电厂蒸汽发生器管模态分析有效方法的开发与应用

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摘要

A typical pressurized water reactor (PWR) steam generator has approximately 10,000 tubes. These tubes have different geometries, supporting conditions, and different material properties due to the non-uniform temperature distribution throughout the steam generator. Even though some tubes may have the same geometry and boundary conditions, the non-uniform distribution of coolant densities adjacent to the tubes causes them to have different added mass effects and dynamic characteristics. Therefore, for a reliable design of the steam generator, a separate modal analysis for each tube is necessary to perform the FIV (flow-induced vibration) analysis. However, the modal analysis of a tube including the finite element modeling is cumbersome and takes lots of time. And when a commercial finite element code is used, interfacing the modal analysis result, such as natural frequencies and mode shapes, with the FIV analysis procedure requires an additional significant amount of time and can possibly incur inadvertent error due to the complexity of data processing. It is therefore impossible to perform the complete FIV analysis for ten thousands of tubes when designing or maintaining a steam generator although it is necessary. Rather, to verify the safe design against the FIV, only a couple of tubes are chosen based on engineering judgment or past experience. In this paper, a computer program, PIAT-MODE, was developed which is able to perform modal analysis of all tubes of a PWR steam generator in a very efficient way. The geometries and boundary conditions of every tube were incorporated into PIAT-MODE using appropriate mathematical formulae. Material property data including the added mass effect was also included in the program. Once a specific tube is selected, the program automatically constructs the finite element model and generates the modal data very quickly. Therefore, modal analysis can be performed for every single tube in a straight way. When PIAT-MODE is coupled with the FTV analysis program, it gives an amazing benefit, which makes the FIV analysis of all tubes possible within a limited time during the design or maintenance period. Using the developed program, the stability ratio regarding the fluid-elastic instability and the amplitude of vibration resulting from the turbulence flow excitation can be calculated for all tubes according the standard ASME Code, therefore, much more reliable design of the steam generator against the FIV related failures can be achieved. For an operating plant, there is a requirement that every single tube must be quantitatively checked whether wear would be more than 40% in thickness during the next operation period. If yes, the tube must be plugged to prevent severe failure including the tube wall penetration. In order to decide the tube plugging, which leads the plant performance degradation, the wear prediction is required. The wear prediction analysis needs wear data by ultrasonic testing and modal property data of tubes. PIAT-MODE will be a power tool enabling the wear prediction in a limited maintenance period by supplying modal data for all tubes.
机译:典型的压水堆(PWR)蒸汽发生器大约有10,000个管。由于整个蒸汽发生器的温度分布不均匀,因此这些管具有不同的几何形状,支撑条件和不同的材料特性。即使某些管道可能具有相同的几何形状和边界条件,但邻近管道的冷却剂密度的不均匀分布也会使它们具有不同的附加质量效应和动态特性。因此,为了可靠地设计蒸汽发生器,必须对每个管子进行单独的模态分析,以执行FIV(流致振动)分析。然而,包括有限元建模的管的模态分析是麻烦的并且花费大量时间。而且,当使用商业有限元代码时,将模态分析结果(例如固有频率和振型)与FIV分析过程相连接需要额外的大量时间,并且由于数据处理的复杂性可能会导致疏忽大意的错误。因此,尽管有必要,但在设计或维护蒸汽发生器时,不可能对上万个试管进行完整的FIV分析。相反,为了验证针对FIV的安全设计,仅根据工程判断或过去的经验选择了几根试管。在本文中,开发了一种计算机程序PIAT-MODE,它能够以非常有效的方式对PWR蒸汽发生器的所有管道进行模态分析。使用适当的数学公式将每个管的几何形状和边界条件合并到PIAT-MODE中。程序中还包括包括附加质量效应在内的材料特性数据。一旦选择了特定的管,程序将自动构建有限元模型并非常快速地生成模态数据。因此,可以直接对每个管进行模态分析。当PIAT-MODE与FTV分析程序结合使用时,它会带来惊人的好处,这使得在设计或维护期间的有限时间内对所有试管进行FIV分析成为可能。使用开发的程序,可以根据标准ASME规范为所有管计算关于流体弹性不稳定性的稳定比和由湍流激发引起的振动幅度,因此,蒸汽发生器针对FIV的设计更加可靠可以实现相关的失败。对于作业工厂,要求必须定量检查每个单根管子,在下一个作业期间,其磨损厚度是否会超过40%。如果是,则必须堵塞管子以防止严重故障,包括管壁穿透。为了确定导致设备性能下降的管道堵塞,需要进行磨损预测。磨损预测分析需要通过超声波测试获得的磨损数据和管的模态特性数据。 PIAT-MODE将成为一种动力工具,通过为所有管子提供模态数据,可以在有限的维护期内进行磨损预测。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2010年第10期|p.3669-3676|共8页
  • 作者单位

    Dept of Mechanical & Aerospace Engineering, Sunchon National University, Sunchon. 540-742, Republic of Korea;

    Korea Hydro and Nuclear Power Company, Yuseong-Gu, Daejeon 305-343, Republic of Korea;

    KEPCO Research Institute, Yuseong-Gu, Daejeon 305-380, Republic of Korea;

    Department of Aerospace Engineering, Chonbuk National University, 664-14, Deogjin-Dongjeonju 561-756, 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
  • 关键词

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