Flow-Induced Vibration Handbook for Nuclear and Process Equipment. Группа авторов. Читать онлайн. Newlib. NEWLIB.NET

Автор: Группа авторов
Издательство: John Wiley & Sons Limited
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Жанр произведения: Физика
Год издания: 0
isbn: 9781119810988
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M. J., and Campagna, A. O., 1979, “ Heat Exchanger Vibration: Comparison Between Operating Experiences and Vibration Analysis,” Proceedings of the International Conference on Practical Experiences with Flow‐Induced Vibrations, Karlsruhe, Germany, 1979 September, (also Atomic Energy of Canada Report, AECL‐6785).

      10 Pettigrew, M. J., Sylvestre, Y. and Campagna, A. O., 1977, “Flow-Induced Vibration Analysis of Heat Exchanger and Steam Generator Designs,” 4th International Conference on Structural Mechanics in Reactor Technology, Paper No. F6/1+, San Francisco, California, Aug. 15‐19, (also Atomic Energy of Canada Report, AECL‐5826).

      11 Pettigrew, M. J., Carlucci, L. N., Taylor, C. E. and Fisher, N. J., 1991, “Flow‐Induced Vibration and Related Technologies in Nuclear Components,” Nuclear Engineering and Design, 131, pp. 81–100.

      12  Rao, M. S. M., Steininger, D. A., and Eisinger, F. L., 1988, “Numerical Simulation of Fluidelastic Vibration and Wear of Multispan Tubes with Clearances at Supports,” Proceedings of the ASME Symposium on Flow‐Induced Vibration and Noise‐1988: Vol. 5, Flow‐Induced Vibration in Heat‐Transfer Equipment, pp. 235–250.

      13 Sauvé, R. G. and Teper, W. W., 1987, “Impact Simulation of Process Equipment Tubes and Support Plates‐A Numerical Algorithm”, Journal of Pressure Vessel Technology, 109, pp. 70–79.

      Notes

      1 1 CANDU‐BLW = Canada Deuterium Uranium – Boiling Light‐Water is a registered trademark of Atomic Energy of Canada Limited.

      2 2 CANDU‐PHW = Canada Deuterium Uranium – Pressurized Heavy‐Water is a registered trademark of Atomic Energy of Canada Limited.

       Michel J. Pettigrew and Colette E. Taylor

      Failures due to excessive vibration must be avoided in process equipment, preferably at the design stage. Thus, a comprehensive flow‐induced vibration analysis is required before fabrication of process equipment, such as shell‐and‐tube heat exchangers. It must be shown that tube vibration levels are below allowable levels and that unacceptable resonances and fluidelastic instabilities are avoided.

      The purpose of this chapter is to summarize our design guidelines for flow‐induced vibration in components operating in gas, liquid, and two‐phase flows. This overview chapter can be used by the designer as a guideline for vibration analysis, by the project engineer to get an overall appreciation of flow‐induced vibration concerns, or by the plant operator to understand tube failures. This overview pertains to critical regions of shell‐and‐tube heat exchangers, such as nuclear steam generators (SG), heat exchangers (HX), coolers, condensers and moisture‐separator‐reheaters (MSR).

      2.1.1 Flow‐Induced Vibration Overview

      The vibration behavior of process system components is governed by vibration excitation mechanisms and by damping mechanisms. Generally, in components such as heat exchangers there are several significant damping mechanisms: 1) friction damping between tube and tube support, 2) squeeze‐film damping at the support, 3) viscous damping between tube and shell‐side fluid, and 4) damping due to two‐phase flow.

      Generally, the flow in heat exchanger tube bundles can be parallel (axial flow) or transverse (cross flow) to the tube. In nuclear steam generators, the flow is axial for a large portion of the tube bundle. Vibration excitation forces induced by axial flow are relatively small in heat exchangers. Thus, vibration excitation mechanisms in axial flow may generally be neglected. The vibration behavior is clearly governed by cross‐flow vibration excitation mechanisms.

      2.1.2 Scope of a Vibration Analysis

      A heat exchanger vibration analysis consists of the following steps: 1) flow distribution calculations, 2) dynamic parameter evaluation (i.e., damping, effective tube mass, and dynamic stiffness), 3) formulation of vibration excitation mechanisms, 4) vibration response prediction, and 5) resulting damage assessment (i.e., comparison against allowables). The requirements applicable to each step are outlined in this overview. Each step is discussed in more detail in the following chapters of this handbook.

      Flow‐induced vibration problems usually occur on a small number of vulnerable tubes in specific areas of a component (e.g., piping elements, entrance regions and tube‐free lanes in heat exchangers, and U‐tubes in nuclear steam generators). Thus, a flow analysis is required to obtain the local flow conditions throughout these heat exchange components. Flow considerations are discussed in detail in Chapter 3.

      2.2.1 Flow Parameter Definition

      The end results of a flow analysis are the shell‐side cross‐flow velocity, Up, and fluid density, ρ, distributions along critical tubes. For flow‐induced vibration analyses, flow velocity is defined in terms of the pitch velocity:

      (2‐1)equation

      where U is the free stream velocity (i.e., the velocity that would prevail if the tubes were removed), P is the pitch between the tubes and D is the tube diameter. For finned tubes, the equivalent or effective diameter, Deff, is used. The pitch velocity is sometimes called the reference gap velocity. The pitch velocity is a convenient definition since it applies to all bundle configurations.

      The situation is somewhat more complex in two‐phase flow. Another parameter, steam quality or void fraction, is required to define the flow conditions. Two‐phase mixtures are rarely homogeneous or uniform across a flow path. However, it is convenient and simple to use homogeneous two‐phase mixture properties as they are well defined. This is done consistently here for both specifying vibration guidelines and formulating vibration mechanisms. The homogeneous void fraction, εg, is defined in terms of the volume flow rates of gas, images, and liquid, Скачать книгу