Flow-Induced Vibration Handbook for Nuclear and Process Equipment. Группа авторов
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Publishing Limited, Oxford, GB, reproduced with permission of Oxford Publishing Limited through PLSclear.
Figures from AERE reports reproduced with the permission of UKAEA Scientific Publications.
Figures from Washington State University Reports reprinted with permission from the Washington State University Libraries.
Figures from the 8th International Heat Transfer Conference reprinted with permission from Begell House Inc.
Figures from the Journal of Heat Transfer Engineering and the Journal of Nuclear Science and Engineering, reprinted with permission of the publisher (Taylor & Francis Ltd, https://www.tand‐fonline.com/)
Figures from Atomic Energy of Canada Ltd. Reports, used with permission from AECL.
This document is based on some 40 years of research and development conducted at Chalk River Laboratories in the area of flow‐induced vibration. This technology development effort was largely supported by Atomic Energy of Canada Limited (AECL) and by the CANDU Owners Group (COG). It also received support from the Heat Transfer and Fluid Flow Service (HTFS), the Centre d’Etudes Nucleaires de Saclay (CEN‐Saclay), the Pressure Vessel Research Council (PVRC) and the Washington Public Power Supply System (WPPSS). The support of all these organizations is very gratefully acknowledged. Many people have contributed to this effort including colleagues from industry and universities. Recognizing that we will fail to acknowledge all of our partners, we have decided to name some of the key individuals and institutions.
The authors have benefited from discussions with researchers in other institutions such as F. Axisa and B. Villard, Centre d’Etudes Nucleaires de Saclay; H.G.D. Goyder, UKAEA Harwell; R.T. Hartlen, Ontario Hydro; N.W. Mureithi and many graduate students at École Polytechnique, Montreal; I.G. Currie, University of Toronto; R.J. Rogers, University of New Brunswick and M.P. Païdoussis, McGill University.
Visiting scientists, B.S. Kim, Korea Power Engineering Company Inc., Taejon, Korea; A. Yasuo, Central Research Institute of Electric Power Industry, Japan; and Z.L. Qiao, Xian Jiaotong University, China, contributed to the development of the flow‐induced vibration database.
The contributors would also like to recognize the input of colleagues from the Canadian Nuclear Laboratories throughout the past 50 years: J. Albrecht, K.M. Boucher, W.A. Cook, T. Dickinson, P. Feenstra, E.G. Hagberg, Y. Han, G. Knowles, J. Mastorakos, J. McGregor, K. Moore, J.N. Patrick, P.J. Smith, Y. Sylvestre, J. H. Tromp, M.K. Weckwerth, and T. Whan. These individuals ably assisted with construction, instrumentation and installation of various flow loops and test sections, as well as copious data analysis.
Finally, the authors wish to express our gratitude to our understanding partners in life, for allowing us to take the time to write this handbook and for their moral support.
Contributors
Liberat N. Carlucci Retired, Canadian Nuclear Laboratories (previously, Atomic Energy of Canada Ltd.)
Nigel J. Fisher Retired, Canadian Nuclear Laboratories (previously, Atomic Energy of Canada Ltd.)
Daniel J. Gorman Professor Emeritus, Ottawa University (Deceased)
Fabrice M. Guérout Canadian Nuclear Laboratories
Victor P. Janzen Retired, Canadian Nuclear Laboratories (previously, Atomic Energy of Canada Ltd.)
Michel J. Pettigrew Principal Engineer Emeritus, Canadian Nuclear Laboratories Adjunct Professor, Polytechnique Montreal
John M. Pietralik Retired, Canadian Nuclear Laboratories (previously, Atomic Energy of Canada Ltd.)
Bruce A. W. Smith Retired, Canadian Nuclear Laboratories (previously, Atomic Energy of Canada Ltd.)
Colette E. Taylor Retired, Canadian Nuclear Laboratories (previously, Atomic Energy of Canada Ltd.)
David S. Weaver Professor Emeritus, McMaster University
Metin Yetisir Canadian Nuclear Laboratories
1 Introduction and Typical Vibration Problems
Michel J. Pettigrew
1.1 Introduction
Excessive flow‐induced vibration must be avoided in process and nuclear system components. That is the purpose of this handbook. The term “process components” is used generally here to describe nuclear reactor internals, nuclear fuels, piping systems, and all shell‐and‐tube heat exchangers, including nuclear steam generators, power plant condensers, boilers, coolers, etc. Higher heat‐transfer performance often requires higher flow velocities and more structural supports. On the other hand, additional supports may increase pressure drop and costs. The combination of high flow velocities and inadequate structural support may lead to excessive tube vibration. This vibration can cause failures by fatigue or fretting wear. Failures are very undesirable in terms of repair costs and lost production, particularly for high‐capital‐cost plants such as nuclear power stations, petroleum refineries and oil exploitation platforms. To prevent these problems at the design stage, a thorough flow‐induced vibration analysis is recommended. Such analysis requires good understanding of the dynamic parameters and vibration excitation mechanisms that govern flow‐induced vibration.
This handbook covers all relevant aspects of component vibration technology, namely: examples of vibration failures, flow analysis, and vibration excitation and damping mechanisms. The latter includes fluidelastic instability, periodic wake shedding, acoustic resonance, random turbulence, flow‐induced vibration analysis and fretting‐wear predictions.
Chapter 2 is an overview of flow‐induced vibration technology. The reader should start with this chapter. In many cases, Chapter 2 will be sufficient to provide the required information. Each aspect of the technology is covered in detail in the succeeding chapters. Typically, each chapter includes a review of the state of the art, available laboratory data, brief review of theoretical considerations and modeling, parametric analysis, recommendations for design, and sample calculations.
The performance of process components is often limited by excessive vibration in a localized area, e.g., near inlets, outlets, etc. The combination of detailed flow calculations and vibration technology allows the designer to avoid such problems. Flow velocities and support design can be optimized to allow maximum heat transfer in all regions of process components, resulting in higher heat‐transfer performance, less corrosion and fouling problems and reduced component size. The latter means capital cost reduction and a more competitive manufacturing industry.
This handbook is for the practicing engineer who is designing or troubleshooting nuclear and process system components. Design guidelines are proposed based on extensive analysis of the literature and, in particular, on experimental data obtained in the field and at the Canadian Nuclear Laboratories of Atomic Energy of Canada Limited at Chalk River, Ontario, Canada. Although it is not intended as an undergraduate text book, it could be useful as a source of design data and practical examples. To assist students and new design engineers, the example calculations provided throughout this handbook are supplemented and presented with more explanation in Appendix A.
There are already several useful books on flow‐induced vibration, e.g. Au‐Yang (2001), Blevins (1990), Chen (1987), Kaneko et al (2014), Naudascher and Rockwell (1994), and Païdoussis (1998). So, why another one in the form of a handbook? This book is complementary to the above books for the following reasons. This book has greater emphasis on design guidelines. Much experimental data is presented in the