Infrastructure Systems for Nuclear Energy

Developing sufficient energy resources to replace coal, oil and gas is a globally critical necessity. Alternatives to fossil fuels such as wind, solar, or geothermal energies are desirable, but the usable quantities are limited and each has inherent deterrents. The only virtually unlimited energy source is nuclear energy, where safety of infrastructure systems is the paramount concern.  Infrastructure Systems for Nuclear Energy addresses the analysis and design of infrastructures associated with nuclear energy. It provides an overview of the current and future nuclear power industry and the infrastructure systems from the perspectives of regulators, operators, practicing engineers and research academics. This book also provides details on investigations of containment structures, nuclear waste storage facilities and the applications of commercial/academic computer software.  Specific environments that challenge the behavior of nuclear power plants infrastructure systems such as earthquake, blast, high temperature, irradiation effects, soil–structure interaction effect, etc., are also discussed.  Key features: • Includes contributions from global experts representing academia and industry • Provides an overview of the nuclear power industry and nuclear infrastructure systems • Presents the state–of–the–art as well as the future direction for nuclear civil infrastructure systems Infrastructure Systems for Nuclear Energy is a comprehensive, up–to–date reference for researchers and practitioners working in this field and for graduate studies in civil and mechanical engineering. INDICE: Preface 1 Introduction 1.1 International Workshop on Infrastructure Systems for Nuclear Energy 1.2 Overview of Nuclear Power Plants 1.3 Infrastructure for Nuclear Power Industry 1.4 Containment Structures 1.5 Nuclear Waste Storage Facilities Part I Infrastructure for Nuclear Power Industry 2 Current Status and Future Role of Nuclear Power Philip G. Tipping 2.1 Introduction 2.2 Installed Nuclear Power Capacity in 2011 2.3 Discussion 2.4 Conclusions 2.5 Sources of Further Information References 3 Seismic Probabilistic Risk Assessment for Nuclear Power Plants Yin–Nan Huang and Andrew S. Whittaker 3.1 Introduction 3.2 Conventional SPRA Methodologies 3.3 The Methodology of Huang et al. 3.4 Summary and Conclusions References 4 Seismic Abatement Method for NPP and Seismic–Isolation Systems for Structural Elements Evgeny Kurbatskiy 4.1 Main Principles of the Method 4.2 Theorem and Proof  4.3 Finite Element Construction 4.4 Pros and Cons of the Method 4.5 Application of the Method to Seismic Isolation Design of Whole Building 4.6 Seismic Isolation Devices to Protect Various Elements and Units 4.7 Applications 4.8 Conclusions 5 Framework for Design of Next–Generation Base–Isolated Nuclear Structures Eric Keldrauk, Michael Mieler, Bo idar Stojadinovi?, and Per Peterson 5.1 Introduction 5.2 Development of Seismic Isolation Systems 5.3 Seismic Isolation of New Nuclear Power Plant Structures 5.4 Performance–Based Design and Evaluation Framework 5.5 Conclusions References 6 Development of Nuclear Energy in Taiwan Hwai–Chiung Hsu 6.1 Introduction 6.2 Brief Illustration for Nuclear Power Plants 6.3 Safety of Nuclear Power Generation 6.4 Nuclear Safety Enhancement 6.5 Radioactive Waste Management 6.6 Conclusions 7 Regulatory Challenges on Safety of Nuclear Power Plants in Taiwan Chuen–Horng Tsai, Yi–Bin Chen, Syh–Tsong Chiou, Shin Chang, Shen–Yu Lai,  Wen–Chun Teng, Gung–Min Ho, Wen–Chuan Chen and Ta–Kang Hsiung 7.1 Introduction 7.2 Challenge I ? New Evidence of Active Faults Near Plants 7.3 Challenge II ? License Renewal and Aging Management 7.4 Challenge III ? Risk–Informed Inservice Inspection 7.5 Challenge IV ? Chinshan ISFSI Program 7.6 Concluding Remarks References 8 Concrete Properties, Safety and Sustainability of Nuclear Power Plant Infrastructures: New Tools and Themes for Future Research Jacky Mazars, Bruno Capra, Alain Rouquand, and Christophe Pontiroli 8.1 Introduction 8.2 Tools for Design and Analysis: Advanced Damage Modeling 8.3 Application to Reinforced Concrete Structures 1 8.4 Ageing Monitoring 8.5 Perspectives and Conclusions References 9 Small Modular Reactors: Infrastructure and Other Systems David Diamond 9.1 Introduction 9.2 Advantages of SMRs 9.3 Regulatory and Technical Issues1 9.4 Design Features of iPWRs 9.5 Conclusions Part II Containment Structures 10 Seismic Design of Reinforced Concrete Structures in Japan – NPP Facilities and High–Rise Buildings Tetsuo Kubo 10.1 Introduction 10.2 Safety Review System of Facilities in Japan 10.3 Design Earthquake Motion for Structures 10.4 Modeling of Structures for a Resdponse Analsyis 10.5 Design Criteria of Structures 10.6 Concluding Remarks References 11 Nonlinear Modeling of 3D Structural Reinforced Concrete and Seismic Performance Assessment Koichi Maekawa and Naoyuki Fukuura 11.1 Introduction 11.2 Fundamentals 11.3 In–Plane Shear Behavior Models 11.4 Experimental Programs 11.5 Conclusions References 12 Shear Ductility and Energy Dissipation of RC Walls Thomas T. C. Hsu 12.1 Introduction 12.2 Shear Theory 12.3 Softened Membrane Model (SMM) 12.4 Conversion of Biaxial Strains to Uniaxial Strains 12.5 Constitutive Model of Concrete in CSMM 12.6 Constitutive Model of Mild Steel Bars in CSMM 12.7 Hysteretic Loops 12.8 Cyclic Shear Ductility and Energy Dissipation 12.9 Framed Shear Walls Under Cyclic Loading 12.10 Earthquake Application 12.11 Conclusions References 13 Behavior of Reinforced Concrete Elements Subjected to Tri–Directional Shear Stresses Moheb Labib, Yashar Moslehy, and Ashraf Ayoub 13.1 Introduction 13.2 Previous Research Studies on Structures Subjected to a 3D State of Stress 13.3 Modeling of RC Elements under a 3D State of Stress 13.4 The Universal Panel Tester 13.5 Installation of Out–of–Plane Hydraulic Cylinders 13.6 Application of Out–of–Plane Shear in the Universal Panel Tester 13.7 Test Program 13.8 Behavior of Test Panels Under Tri–Directional Shear Loads 13.9 Interaction Surface of Bi–Directional Shear Stresses 13.10 Summary and Conclusions References 14 Prestressed Concrete Containment Structural Design in China Zufeng Xia 14.1 Introduction 14.2 Design Improvements of Prestressed Concrete Containment in Chashma Nuclear Power Plant 14.3 Overview of the Performance Analysis and Experiment Investigation on Research subjects of the Third–Generation Containments 14.4 Applications of Other Containment Structures in Domestic Nuclear Power Plants 14.5 Concept Design of Spherical Prestressed Concrete Containment Structures 14.6 Design Experiences of Prestressed Concrete Containments References 15 Steel Plate Concrete Walls for Containment Structures in Korea: In–Plane Shear Behavior Sung–Gul Hong, Seung–Joon Lee, and Myung–Jae Lee 15.1 Introduction 15.2 Fundamentals 15.3 In–Plane Shear Behavior Models 15.4 Experimental Programs 15.5 Conclusions References 16 Lessons Learned from Kashiwazaki–Kariwa NPP at Niigataken Chuetsu–Oki Earthquake (2007) in Viewpoint of SSI Effect T. Nishikawa, H. Inoue, S. Motohashi, and K. Ebisawa 16.1 Introduction 16.2 Outline of the Earthquake, KK–NPP and Observed Events 16.3 Simulation Analyses of Observation Records 16.4 Study of Some Factors Effect on Floor Response of Building 16.5 Conclusions 17 Blast, Shock, and Impact Hazards to Nuclear Structures Theodor Krauthammer 17.1 Introduction 17.2 Fundamentals 17.3 In–Plane Shear Behavior Models 17.4 Experimental Programs 17.5 Conclusions References 18 History of Shear Design Provisions in ASME/ACI Code for Concrete  Reactor Vessels and Containments Ralph G. Oesterle, W. Gene Corley, and Ahmed Elremaily 18.1 Introduction 18.2 Background of ASME/ACI Code 18.3 Tangential Shear Design Provisions 18.4 Peripheral Shear Design Provisions 18.5 Radial Shear Design Provisions 18.6 Summary References 19 U.S. NRC Requirements for Containment Structure Design John S. Ma, Bret A. Tegeler, Bret A. Tegeler, and Brian E. Thomas 19.1 Introduction 19.2 Seismic Analysis for Containment Structures 19.3 Design of Containment Structure 19.4 Conclusions Part III Computer Software for Containment Structures 20 FE Program SCS for Analyzing Wall–Type Concrete Structures Y.L. Mo, Padmanabha Rao Tadepalli, Norman Hoffman, and Thomas T.C. Hsu 20.1 Introduction 20.2 Material Scale 20.3 Element Scale 20.4 Structure Scale 20.5 Validation 20.6 Conclusions References 21 Modeling and Analysis of Nuclear Power Plant Structures Using ANATECH–ANACAP Software System Joseph YR Rashid, Randy J. James, and Robert S. Dunham 21.1 Introduction 21.2 Concrete Constitutive Formulation in Anacap–U 21.3 Example Applications References 22 SASSI FE Program for Seismic Response Analysis of Nuclear Containment Structures Mansour Tabatabaie 22.1 Introduction 22.2 Methodology 22.3 Summary References 23 FE Program LS–DYNA for Analysis of NPP Structures Including Seismic Soil–Structure Interaction Ushnish Basu 23.1 Introduction 23.2 Relevant Strengths of LS–DYNA 23.3 Analysis Framework 23.4 Perfectly Matched Layer (PML) 23.5 Effective Seismic Input 23.6 Numerical Results 23.7 Conclusions References 24 FE Program ATENA for Safety Assessment of NPP Containments Jan Cervenka and Vladimir Cervenka 24.1 Introduction 24.2 Material Model for Concrete 24.3 Validation 24.4 Non–Linear Analysis of Containment Structures 24.5 Closing Remarks References Part IV   Nuclear Waste Storage Facilities 25 Properties of Concrete Required in Nuclear Power Plants Patrick Bamonte and Pietro G. Gambarova 25.1 Introduction 25.2 Chemical Attack, Freezing and Thawing Cycling 25.3 Permeability and Diffusivity 25.4 Radiation Shielding Capability and Irradiation Effects 25.5 Volume Changes and Creep 25.6 Thermal and Fire Exposure 25.7 Concrete for Waste–Disposal Structures 25.8 Conclusions References 26 Concrete under High Temperature Kaspar Willam, Yunping Xi, and Daniel J. Naus 26.1 Introduction 26.2 The Coupling Among Hygro–Thermo–Mechanical Loading 26.3 Modeling Coupling 26.4 Acceleration of Basic Creep of Concrete by Temperature 26.5 Experimental Data 26.6 High Temperature Test Data 26.7 Concrete Strength Data 26.8 Remarks on Temperature Concrete Data 26.9 Thermo–Elastoplastic Concrete Model 26.10 Loss of Bounded Material Response 26.11 Concluding Remarks References 27 Irradiation Effects on Concrete Structures Osamu Kontani, Yoshikazu Ichikawa, Akihiro Ishizawa, Masayuki Takizawa, and Osamu Sato 27.1 Introduction 27.2 Background 27.3 Microstructures 27.4 Interaction Between Radiation and Materials 27.5 Mechanism of Concrete Deterioration 27.6 Gamma Ray Irradiation Tests 27.7 Conclusions References 28 Activities in Support of Continuing the Service of Nuclear Power Plant Safety–Related Concrete Structures D. J. Naus 28.1 Introduction 28.2 Concrete Structures 28.3 In–Service Inspection and Testing Requirments 28.4 Renewal of Operating Licenses 28.5 Operating Experience and Material Performance 28.6 Management of Aging 28.7 Potential Research Topics 28.8 Summary References 29 Spent Nuclear Fuel Final Disposal in Taiwan Y. C. Peng 29.1 Introduction 29.2 Disposal Program 29.3 Operation Organization and Work Delegation 29.4 Nuclear Backend Fund 29.5 2009 Progress Report 29.6 Conclusions References 30 Safety Features of Dry Storage System at Chinshan NPP Yuhao Huang 30.1 Introduction 30.2 Major Components and Operation Sequence 30.3 Major Safety Features 30.4 Concluding Remarks References 31 Seismic Consequence Modeling for the Yucca Mountain Repository Project Andrew Orrell and Charles Bryan 31.1 Introduction 31.2 Description of the Repository 31.3 The PREclosure Safety Case 31.4 The Postclosure Safety Case 31.5 Summary References

• ISBN: 978-1-119-97585-4
• Editorial: Wiley–Blackwell
• Encuadernacion: Cartoné
• Páginas: 584
• Fecha Publicación: 17/01/2014
• Nº Volúmenes: 1
• Idioma: Inglés