Flow-Induced Vibration Handbook for Nuclear and Process Equipment. Группа авторов
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Anti‐vibration bars (AVBs) are often used in the U‐bend region of nuclear steam generators. AVBs are reasonably effective in the out‐of‐plane direction, but offer little restraint in the in‐plane (plane of the U‐bend) direction (Taylor et al, 1995). Fortunately, the vibration response is usually much less in the in‐plane direction than in the out‐of‐plane direction. Nevertheless, AVBs are less effective than other clearance supports. For steam generator vibration analyses, it is recommended that one (any one) AVB in the U‐bend region be assumed ineffective. The possibility that two adjacent AVBs would be ineffective at the same time is considered too improbable to be of concern. For example, if we assume that the probability of one AVB being ineffective is less than one percent, then the probability of two adjacent AVBs being ineffective is less than 0.01% or less than one tube in 10 000, which is less than one tube per steam generator and, thus, insignificant.
In the in‐plane direction, on the other hand, recent experience has shown that more than one adjacent AVB may be ineffective and that maybe two or more AVBs should be assumed ineffective in the in‐plane direction. In practice, tube‐to‐support clearances must be small enough to provide an effective support. Thus, pinned support conditions may be assumed provided that the tube‐to‐support diametral clearance for drilled holes, broached holes, scallop bars, egg crates and lattice bars is equal to or less than 0.4 mm. In the out‐of‐plane direction, the diametral clearance between tube and AVBs should be sufficiently small to provide effective support (e.g., <0.1 mm).
2.4 Vibration Excitation Mechanisms
As mentioned previously in Section 2.1.1, several vibration mechanisms are normally considered in heat exchange components: fluidelastic instability, random turbulence excitation, periodic wake shedding and acoustic resonance. Formulations for these mechanisms are presented in the following sub‐sections (Sections 2.4.1 to 2.4.5) of this chapter. More details are given in Chapters 7 to 11.
2.4.1 Fluidelastic Instability
Fluidelastic instability is the most severe vibration excitation mechanism in heat exchanger tube bundles. Formulations for single‐ and two‐phase cross flow are given below. The topics are discussed in more detail in Chapters 7 and 8 for single‐ and two‐phase flow, respectively.
Single‐Phase Cross Flow (Gas or Liquid)
Fluidelastic instability for tube bundles subjected to single‐phase cross flow was reviewed by Pettigrew and Taylor (1991). Fluidelastic instability is formulated in terms of a dimensionless flow velocity, Up/fD and a dimensionless mass‐damping parameter, 2πζm/ρD2, such that:
where f is the tube natural frequency, ρ is the fluid density, m is the tube mass per unit length and Upc is the threshold, or critical, flow velocity for fluidelastic instability. A fluidelastic instability constant K = 3.0 is recommended for all tube bundle configurations, as shown in Fig. 2-11 (Pettigrew and Taylor, 1991). The damping ratio, ζ, is the total damping ratio as outlined in Section 2.3.2. The above formulation applies to all cross‐flow regions such as steam generator preheater regions, heat‐exchanger tube bundles between baffle plates, and outlet and inlet regions.
Two‐Phase Flow
We have found that fluidelastic instability behavior is somewhat similar in continuous two‐phase cross flow, (Pettigrew et al, 1989b). As explained in Chapter 3, continuous flow means two‐phase flow regions of a continuous nature such as bubbly, spray, fog and wall flows as opposed to intermittent flow regimes leading to bundle reflooding and large flow oscillations. Such oscillations can lead to much lower critical velocity for fluidelastic instability (Pettigrew et al, 1989b, 1995 and 1994). Thus, intermittent flow regimes should be avoided in two‐phase cross flow.
Fig. 2-11 Summary of Fluidelastic Instability Data for Single‐Phase Cross Flow: Recommended Design Guidelines.
Fig. 2-12 Fluidelastic Instability Data in Two‐Phase Cross Flow.
Fluidelastic instability in two‐phase cross flow can also be formulated using Eq. (2-25). As shown in Fig. 2-12, a fluidelastic instability constant K = 3.0 is also recommended for two‐phase cross flow, but only for tube bundles of P/D > 1.47 which is the case for many steam generators. Lower values of K must be used for bundles of P/D ratios lower than 1.47, as discussed by Pettigrew and Taylor (1994). As shown in Fig. 2-13, the expression
(2‐26)
would be a reasonable design guideline for P/D < 1.47.
2.4.2 Random Turbulence Excitation
Random turbulence excitation is a significant excitation mechanism in both liquid and two‐phase cross flow. Formulations for single‐ and two‐phase cross flow are given below. The topics are discussed in more detail in Chapters 9 and 10 for single‐ and two‐phase flow, respectively.
To be able to compare data and find an upper bound, the excitation forces must be presented as a normalized excitation force spectra. Researchers in this field such as