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Author: Wei-Chau Xie Publisher: Cambridge University Press ISBN: 1108752608 Category : Technology & Engineering Languages : en Pages : 631
Book Description
Seismic Risk Analysis of Nuclear Power Plants addresses the needs of graduate students in engineering, practicing engineers in industry, and regulators in government agencies, presenting the entire process of seismic risk analysis in a clear, logical, and concise manner. It offers a systematic and comprehensive introduction to seismic risk analysis of critical engineering structures focusing on nuclear power plants, with a balance between theory and applications, and includes the latest advances in research. It is suitable as a graduate-level textbook, for self-study, or as a reference book. Various aspects of seismic risk analysis - from seismic hazard, demand, and fragility analyses to seismic risk quantification, are discussed, with detailed step-by-step analysis of specific engineering examples. It presents a wide range of topics essential for understanding and performing seismic risk analysis, including engineering seismology, probability theory and random processes, digital signal processing, structural dynamics, random vibration, and engineering risk and reliability.
Author: Wei-Chau Xie Publisher: Cambridge University Press ISBN: 1108752608 Category : Technology & Engineering Languages : en Pages : 631
Book Description
Seismic Risk Analysis of Nuclear Power Plants addresses the needs of graduate students in engineering, practicing engineers in industry, and regulators in government agencies, presenting the entire process of seismic risk analysis in a clear, logical, and concise manner. It offers a systematic and comprehensive introduction to seismic risk analysis of critical engineering structures focusing on nuclear power plants, with a balance between theory and applications, and includes the latest advances in research. It is suitable as a graduate-level textbook, for self-study, or as a reference book. Various aspects of seismic risk analysis - from seismic hazard, demand, and fragility analyses to seismic risk quantification, are discussed, with detailed step-by-step analysis of specific engineering examples. It presents a wide range of topics essential for understanding and performing seismic risk analysis, including engineering seismology, probability theory and random processes, digital signal processing, structural dynamics, random vibration, and engineering risk and reliability.
Author: Wei-Chau Xie Publisher: Cambridge University Press ISBN: 1107040469 Category : Mathematics Languages : en Pages : 631
Book Description
A systematic and comprehensive introduction of seismic risk analysis of critical engineering structures, focusing on nuclear power plants.
Author: Zhaoliang Wang Publisher: ISBN: Category : Languages : en Pages : 216
Book Description
Earthquakes are destructive natural disasters that can inflict various levels of damage on engineering structures and lead to other adverse consequences. Accurate seismic risk quantification of critical engineering structures such as nuclear power plants is of great importance, not only for answering public safety concern but also for facilitating risk-informed decision making. Seismic Probabilistic Risk Analysis (SPRA) has been widely used for seismic analysis and design of critical engineering structures. It combines the probabilistic model of the behavior of structural response given a ground-motion parameter (GMP) value (e.g., seismic fragility model) and the Probabilistic Seismic Hazard Analysis (PSHA) for the GMP in a mathematically rigorous manner. However, there are a number of issues on the engineering application of SPRA that need to be addressed before it can be readily implemented into current engineering practice. In current SPRA practice, both the fragility model and PSHA are based on a single GMP, which is adequate for the single-mode-dominant structures. For multiple-mode-dominant structures, whose response could be better predicted using multiple GMP,a vector-valued SPRA is conceptually more appropriate. However, vector-valued SPRA requires extensive computational efforts and extensive consultation of vector-valued PSHA from seismologists,which prevent it from being ready for engineering purposes. The objective of this study is to bridge the gaps between seismological analyses and engineering applications, i.e., to address the immediate issues in current vector-valued SPRA so that it can be readily applied into engineering practice. A new seismic hazard deaggregation procedure is developed for seismic risk analysis, which determines a set of controlling earthquakes that induce dominant hazard to the site of interest. A simplified approach to vector-valued SPRA is developed based on the controlling earthquakes. Integration over all possible earthquake occurrences in standard vector-valued SPRA is then avoided,which substantially improves the computational efficiency without losing accuracy. This overcomes the deficiencies and preserves the advantages of standard vector-valued SPRA. To facilitate performing the simplified approach, factors affecting the accuracy of the simplified approach are discussed and illustrated through the numerical examples. In addition, seismic capacity evaluation of nuclear facilities is an important task in a SPRA. However, following the current evaluation procedures, inconsistency in seismic capacity estimates are often obtained for the same facility in similar plants at different locations. The inconsistency also shows dependency on the GMP selected for defining seismic capacity. This inconsistency is conceptually undesirable for engineering purposes. To characterize the possible factors affecting the consistency in seismic capacity estimates, a comprehensive parametric study is performed in an analytical manner. Theoretical derivations and graphical illustrations are resorted to facilitate the analysis. Both general and case-by-case analyses are performed to show how each of these factors affects the consistency in seismic capacity estimates. This parametric study represents a wide coverage of seismic capacity evaluating problems for nuclear facilities, and hence can be used for interpreting results of similar kinds in current engineering practice.
Author: Robert J. Hansen Publisher: MIT Press (MA) ISBN: 9780262080415 Category : Technology & Engineering Languages : en Pages : 489
Book Description
The development of protective measures to guard against the spread of radioactive debris following reactor disasters has been given extensive and careful engineering attention over the past several years. Much of this attention has been devoted to eliminating or minimizing the effects of malfunctions of internal components. But reactors can also suffer externally caused disasters—for example, their radioactive cores can be damaged by earthquakes or by missiles generated by tornadoes. Earthquakes in particular will continue to render man vulnerable even to the "peaceful atom" as the number of nuclear power plants increases and as they come to be located in those parts of the world that have a history of seismic activity. It was to consider such problems that the seminar reported here was held. The conferees, who are leaders in this special and important field, gathered in Cambridge, Massachusetts, in spring 1969, to present the papers whose titles are listed below. Together they cover both the theoretical underpinnings of the subject and specific applications to nuclear reactors; they provide both useful summaries of what is known to date and some new thinking on the subject, not before published. Contents: Preface—T. J. Thompson. Foreword—R. J. Hansen. Introduction—R. V. Whitman. Geological and Seismological Factors Influencing the Assessment of a Seismic Threat to Nuclear Reactors—Daniel Linehan, S. J. Geophysics—Keiiti Aki. Design Seismic Inputs—C. Allin Cornell. Some Observations on Probabilistic Methods in the Seismic Design of Nuclear Power Plants—C. Allin Cornell. Seismic Risk and Seismic Design Decisions—Luis Esteva. Fundamentals of Soil Amplification—J. M. Roesset. Soil Structure Interaction—R. V. Whitman. Evaluation of Soil Properties for Site Evaluation and Dynamic Analysis of Nuclear Plants—R. V. Whitman. Structural Response to Seismic Input—J. M. Biggs. Seismic Analysis of Equipment Mounted on a Massive Structure—J. M. Biggs and J. M. Roesset. Modal Response of Containment Structures—Peter Jan Pahl. Provision of Required Seismic Resistance—M. J. Holley, Jr. A Measure of Earthquake Intensity—Arturo Arias. Closure—R. J. Hansen.
Author: Publisher: IAEA ISBN: Category : Business & Economics Languages : en Pages : 48
Book Description
This Safety Guide provides guidelines and recommends procedures for the evaluation of seismic hazards for nuclear power plants. Specifically, it provides recommendations on how to determine the ground motion hazards for a plant at a particular site and the potential for surface faulting, which could affect the feasibility of construction and safe operation of a plant at that site. The Guide supersedes IAEA Safety Series No. 50-SG-S1 (Rev.l), Earthquakes and Associated Topics in Relation to Nuclear Power plant Siting that was issued in 1991.
Author: Masanori Hamada Publisher: Springer ISBN: 9811025169 Category : Technology & Engineering Languages : en Pages : 304
Book Description
This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground are explained.
Author: Katsuhiro Kamae Publisher: Springer ISBN: 4431558225 Category : Technology & Engineering Languages : en Pages : 177
Book Description
This book covers seismic probabilistic risk assessment (S-PRA) and related studies which have become more important to increase the safety of nuclear facilities against earthquakes and tsunamis in the face of the many uncertainties after the Fukushima accident. The topics are (1) Active faults and active tectonics important for seismic hazard assessment of nuclear facilities,(2) Seismic source modeling and simulation and modeling techniques indispensable for strong ground motion prediction, and (3) PRA with external hazard and risk communication. The Fukushima accident has showed us the limitations of the deterministic evaluation approach to external events (an earthquake and tsunami) in which there are many uncertainties. Furthermore, public anxiety regarding nuclear safety because of an unexpected threat caused by an earthquake or tsunami is growing. The current policy on the estimation of the design basis of ground motion as well as tsunami height still has not been improved following the Fukushima accident. In particular, the risk concept in a nuclear system regarding seismic motion and a tsunami beyond the design basis is indispensable. Therefore, research and development for PRA enhancing nuclear safety are being actively pursued not only in Japan but also worldwide. This book provides an opportunity for readers to consider the future direction of nuclear safety vis-à-vis natural disasters.
Author: International Atomic Energy Agency Publisher: IAEA ISBN: Category : Business & Economics Languages : en Pages : 76
Book Description
This Safety Guide provides recommendations on a generally accepted way to design a nuclear power plant so that an earthquake motion at the site will not jeopardize the safety of the plant. It also gives guidance on a consistent application of methods and procedures for analysis, testing and qualification of structures and equipment so that they meet the safety requirements covering the design of nuclear power plants, safety assessments for the design and the regulatory issues concerned with the licensing of plants.