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Explains the mechanisms governing flow-induced vibrations and helps engineers prevent fatigue and fretting-wear damage at the design stage Fatigue or fretting-wear damage in process and plant equipment caused by flow-induced vibration can lead to operational disruptions, lost production, and expensive repairs. Mechanical engineers can help prevent or mitigate these problems during the design phase of high capital cost plants such as nuclear power stations and petroleum refineries by performing thorough flow-induced vibration analysis. Accordingly, it is critical for mechanical engineers to have a firm understanding of the dynamic parameters and the vibration excitation mechanisms that govern flow-induced vibration. Flow-Induced Vibration Handbook for Nuclear and Process Equipment provides the knowledge required to prevent failures due to flow-induced vibration at the design stage. The product of more than 40 years of research and development at the Canadian Nuclear Laboratories, this authoritative reference covers all relevant aspects of flow-induced vibration technology, including vibration failures, flow velocity analysis, vibration excitation mechanisms, fluidelastic instability, periodic wake shedding, acoustic resonance, random turbulence, damping mechanisms, and fretting-wear predictions. Each in-depth chapter contains the latest available lab data, a parametric analysis, design guidelines, sample calculations, and a brief review of modelling and theoretical considerations. Written by a group of leading experts in the field, this comprehensive single-volume resource: * Helps readers understand and apply techniques for preventing fatigue and fretting-wear damage due to flow-induced vibration at the design stage * Covers components including nuclear reactor internals, nuclear fuels, piping systems, and various types of heat exchangers * Features examples of vibration-related failures caused by fatigue or fretting-wear in nuclear and process equipment * Includes a detailed overview of state-of-the-art flow-induced vibration technology with an emphasis on two-phase flow-induced vibration Covering all relevant aspects of flow-induced vibration technology, Flow-Induced Vibration Handbook for Nuclear and Process Equipment is required reading for professional mechanical engineers and researchers working in the nuclear, petrochemical, aerospace, and process industries, as well as graduate students in mechanical engineering courses on flow-induced vibration.
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Veröffentlichungsjahr: 2021
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Michel J. Pettigrew, Colette E. Taylor, Nigel J. Fisher
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© 2022 ASMEThis Work is a co-publication between ASME Press and John Wiley & Sons, Inc.
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ISBN: 9781119810964
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Excessive flow‐induced vibration causing failures by fatigue or fretting wear must be avoided in process and nuclear components. That is the purpose of this handbook. In this book, the term process components is used generally to describe nuclear reactor internals, nuclear fuels, piping systems, and all shell‐and‐tube heat exchangers, including nuclear steam generators, power plant condensers, boilers and coolers.
There are already a number of good books on flow‐induced vibration. So, why another one? This handbook is to help engineers to design, operate, and diagnose heat transfer equipment. The emphasis in this handbook is on two‐phase flow‐induced vibration. Despite the fact that roughly half of all heat exchanger equipment operates in two‐phase flow, previous flow‐induced vibration texts have provided limited guidance regarding vibration induced by two‐phase flow. The prediction of fretting‐wear damage is another important priority. The state of the art is presented in the design guidelines, figures and tables. The use of these design guidelines is illustrated with example calculations. To assist students and new design engineers, the calculations are supplemented and presented with more explanation in an appendix.
Largely, this handbook is the outcome of some 40 years of research and development at the Canadian Nuclear Laboratories. The emphasis of this book is the presentation of design guidelines based on extensive analysis of the literature and, in particular, on experimental data obtained in the field and at the Canadian Nuclear Laboratories in Chalk River.
We believe that this book will be useful to engineering design firms in the nuclear, petrochemical and aerospace industries, graduate schools in mechanical engineering and technical support groups in operating nuclear and petrochemical plants. This handbook is not a textbook, although it could be used as a resource in a graduate course. We also hope that this book will help to stimulate further research in the area of two‐phase flow‐induced vibration.
Michel J. Pettigrew
Colette E. Taylor
Nigel J. Fisher
The authors would like to recognize the institutions and colleagues who have provided permissions, support and inspiration to this project. We begin by recognizing the publishers who have kindly given permission to use copyrighted tables and figures. Rather than add the requested recognition statements to each figure, the following general statements are provided to avoid repetition.
Figures from the
Congress of the Engineering Institute of Canada (EIC)
reprinted with permission from the EIC.
Figures from the
International Association for Structural Mechanics in Reactor Technology (IASMiRT) conferences
reprinted courtesy of IASMiRT.
Figures from
ANL Reports
, copyright by Argonne National Laboratory, managed and operated by the University of Chicago, U.S. Department of Energy, reprinted with permission.
Figures from the
Nuclear Power Safety
, the
Journal of Fluids and Structures
, the
Journal of Sound and Vibration
, the
Journal of Multiphase Flow
and the
Journal of Nuclear Engineering and Design
, reprinted with permission from Elsevier.
Figures from
Convective Boiling and Condensation
, Oxford 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
8
th
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.
Liberat N. CarlucciRetired, Canadian Nuclear Laboratories(previously, Atomic Energy of Canada Ltd.)
Nigel J. FisherRetired, Canadian Nuclear Laboratories(previously, Atomic Energy of Canada Ltd.)
Daniel J. GormanProfessor Emeritus, Ottawa University (Deceased)
Fabrice M. GuéroutCanadian Nuclear Laboratories
Victor P. JanzenRetired, Canadian Nuclear Laboratories(previously, Atomic Energy of Canada Ltd.)
Michel J. PettigrewPrincipal Engineer Emeritus, Canadian Nuclear LaboratoriesAdjunct Professor, Polytechnique Montreal
John M. PietralikRetired, Canadian Nuclear Laboratories(previously, Atomic Energy of Canada Ltd.)
Bruce A. W. SmithRetired, Canadian Nuclear Laboratories(previously, Atomic Energy of Canada Ltd.)
Colette E. TaylorRetired, Canadian Nuclear Laboratories(previously, Atomic Energy of Canada Ltd.)
David S. WeaverProfessor Emeritus, McMaster University
Metin YetisirCanadian Nuclear Laboratories
