{"product_id":"infrastructure-systems-for-nuclear-energy-isbn-9781119975854","title":"Infrastructure Systems for Nuclear Energy","description":"\u003cp\u003eDeveloping 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.\u003c\/p\u003e \u003cp\u003e\u003ci\u003eInfrastructure Systems for Nuclear Energy\u003c\/i\u003e 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.\u003c\/p\u003e \u003cp\u003eSpecific 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.\u003c\/p\u003e \u003cp\u003eKey features:\u003c\/p\u003e \u003cul\u003e \u003cli\u003eIncludes contributions from global experts representing academia and industry\u003c\/li\u003e \u003cli\u003eProvides an overview of the nuclear power industry and nuclear infrastructure systems\u003c\/li\u003e \u003cli\u003ePresents the state-of-the-art as well as the future direction for nuclear civil infrastructure systems\u003c\/li\u003e \u003c\/ul\u003e \u003cp\u003e\u003ci\u003eInfrastructure Systems for Nuclear Energy\u003c\/i\u003e is a comprehensive, up-to-date reference for researchers and practitioners working in this field and for graduate studies in civil and mechanical engineering.\u003c\/p\u003e \u003cp\u003eList of Contributors xv\u003c\/p\u003e \u003cp\u003ePreface xix\u003c\/p\u003e \u003cp\u003eAcronyms xxi\u003c\/p\u003e \u003cp\u003e\u003cb\u003e1 Introduction 1\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eThomas T. C. Hsu, Chiun-Lin Wu, and Jui-Liang Lin\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e1.1 International Workshop on Infrastructure Systems for Nuclear Energy 1\u003c\/p\u003e \u003cp\u003e1.2 Overview of Nuclear Power Plants 4\u003c\/p\u003e \u003cp\u003e1.3 Infrastructure for Nuclear Power Industry 5\u003c\/p\u003e \u003cp\u003e1.4 Containment Structures 7\u003c\/p\u003e \u003cp\u003e1.5 Nuclear Waste Storage Facilities 13\u003c\/p\u003e \u003cp\u003e\u003cb\u003ePart One Infrastructure for Nuclear Power Industry\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e\u003cb\u003e2 Current Status and Future Role of Nuclear Power 19\u003cbr\u003e \u003c\/b\u003e\u003ci\u003ePhilip G. Tipping\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e2.1 Introduction 19\u003c\/p\u003e \u003cp\u003e2.2 Installed Nuclear Power Capacity in 2011 21\u003c\/p\u003e \u003cp\u003e2.3 Discussion 28\u003c\/p\u003e \u003cp\u003e2.4 Conclusions 30\u003c\/p\u003e \u003cp\u003e2.5 Further Reading 31\u003c\/p\u003e \u003cp\u003eReferences 33\u003c\/p\u003e \u003cp\u003e\u003cb\u003e3 Seismic Probabilistic Risk Assessment for Nuclear Power Plants 35\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eYin-Nan Huang and Andrew S. Whittaker\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e3.1 Introduction 35\u003c\/p\u003e \u003cp\u003e3.2 Conventional SPRA Methodologies 36\u003c\/p\u003e \u003cp\u003e3.3 The Methodology of Huang et al. 44\u003c\/p\u003e \u003cp\u003e3.4 Summary and Conclusions 48\u003c\/p\u003e \u003cp\u003eReferences 48\u003c\/p\u003e \u003cp\u003e\u003cb\u003e4 Seismic Abatement Method for Nuclear Power Plants and Seismic-Isolation Systems for Structural Elements 51\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eEvgeny Kurbatskiy\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e4.1 Main Principles of the Method 51\u003c\/p\u003e \u003cp\u003e4.2 Theorem and Proof 52\u003c\/p\u003e \u003cp\u003e4.3 Finite Element Construction 53\u003c\/p\u003e \u003cp\u003e4.4 Pros and Cons of the Method 56\u003c\/p\u003e \u003cp\u003e4.5 Application of the Method to Seismic Isolation Design of Whole Building 57\u003c\/p\u003e \u003cp\u003e4.6 Seismic Isolation Devices to Protect Various Elements and Units 58\u003c\/p\u003e \u003cp\u003e4.7 Applications 59\u003c\/p\u003e \u003cp\u003e4.8 Conclusions 61\u003c\/p\u003e \u003cp\u003eReferences 61\u003c\/p\u003e \u003cp\u003e\u003cb\u003e5 Framework for Design of Next-Generation Base-Isolated Nuclear Structures 63\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eEric Keldrauk, Michael Mieler, Božidar Stojadinović, and Per Peterson\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e5.1 Introduction 63\u003c\/p\u003e \u003cp\u003e5.2 Development of Seismic Isolation Systems 65\u003c\/p\u003e \u003cp\u003e5.3 Seismic Isolation of New Nuclear Power Plant Structures 67\u003c\/p\u003e \u003cp\u003e5.4 Performance-Based Design and Evaluation Framework 70\u003c\/p\u003e \u003cp\u003e5.5 Conclusions 73\u003c\/p\u003e \u003cp\u003eReferences 74\u003c\/p\u003e \u003cp\u003e\u003cb\u003e6 Development of Nuclear Energy in Taiwan 77\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eHwai-Chiung Hsu\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e6.1 Introduction 77\u003c\/p\u003e \u003cp\u003e6.2 Brief Illustration of Nuclear Power Plants 78\u003c\/p\u003e \u003cp\u003e6.3 Safety of Nuclear Power Generation 81\u003c\/p\u003e \u003cp\u003e6.4 Nuclear Safety Enhancement 82\u003c\/p\u003e \u003cp\u003e6.5 Radioactive Waste Management 82\u003c\/p\u003e \u003cp\u003e6.6 Conclusions 83\u003c\/p\u003e \u003cp\u003e\u003cb\u003e7 Regulatory Challenges on Safety of Nuclear Power Plants in Taiwan 85\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eChuen-Horng Tsai, Yi-Bin Chen, Shin Chang, Wen-Chun Teng, Ching-Hui Wu, Gung-Min Ho, Ta-Kang Hsiung, Syh-Tsong Chiou, and Wen-Chuan Chen\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e7.1 Introduction 85\u003c\/p\u003e \u003cp\u003e7.2 Challenge I: New Evidence of Active Faults Near Plants 86\u003c\/p\u003e \u003cp\u003e7.3 Challenge II: Aging Management 88\u003c\/p\u003e \u003cp\u003e7.4 Challenge III: Risk-Informed In-Service Inspection (RI-ISI) 92\u003c\/p\u003e \u003cp\u003e7.5 Challenge IV – Chinshan Independent Spent Fuel Storage Installation (ISFSI) Program 94\u003c\/p\u003e \u003cp\u003e7.6 Challenge V: Post-Fukushima Safety Reassessment of NPPs 99\u003c\/p\u003e \u003cp\u003e7.7 Concluding Remarks 101\u003c\/p\u003e \u003cp\u003eReferences 102\u003c\/p\u003e \u003cp\u003e\u003cb\u003e8 Concrete Properties, Safety, and Sustainability of Nuclear Power Plant Infrastructures: New Tools and Themes for Future Research 103\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eJacky Mazars, Bruno Capra, Alain Rouquand, and Christophe Pontiroli\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e8.1 Introduction 103\u003c\/p\u003e \u003cp\u003e8.2 Tools for Design and Analysis: Advanced Damage Modeling 104\u003c\/p\u003e \u003cp\u003e8.3 Application to Reinforced Concrete Structures 110\u003c\/p\u003e \u003cp\u003e8.4 Aging Monitoring 119\u003c\/p\u003e \u003cp\u003e8.5 Perspectives and Conclusions 123\u003c\/p\u003e \u003cp\u003eReferences 124\u003c\/p\u003e \u003cp\u003e\u003cb\u003e9 Small Modular Reactors: Infrastructure and Other Systems 127\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eDavid Diamond\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e9.1 Introduction 127\u003c\/p\u003e \u003cp\u003e9.2 Advantages of SMRs 127\u003c\/p\u003e \u003cp\u003e9.3 Regulatory and Technical Issues 128\u003c\/p\u003e \u003cp\u003e9.4 Design Features of iPWRs 128\u003c\/p\u003e \u003cp\u003e9.5 Conclusions 131\u003c\/p\u003e \u003cp\u003e\u003cb\u003ePart Two Containment Structures\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e\u003cb\u003e10 Seismic Design of Reinforced Concrete Structures in Japan: NPP Facilities and High-Rise Buildings 135\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eTetsuo Kubo\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e10.1 Introduction 135\u003c\/p\u003e \u003cp\u003e10.2 Safety Review System of Facilities in Japan 135\u003c\/p\u003e \u003cp\u003e10.3 Design Earthquake Motion for Structures 137\u003c\/p\u003e \u003cp\u003e10.4 Modeling of Structures for a Response Analsyis 142\u003c\/p\u003e \u003cp\u003e10.5 Design Criteria of Structures 149\u003c\/p\u003e \u003cp\u003e10.6 Concluding Remarks 151\u003c\/p\u003e \u003cp\u003eReferences 152\u003c\/p\u003e \u003cp\u003e\u003cb\u003e11 Nonlinear Modeling of 3D Structural Reinforced Concrete and Seismic Performance Assessment 153\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eKoichi Maekawa and Naoyuki Fukuura\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e11.1 Introduction 153\u003c\/p\u003e \u003cp\u003e11.2 Construction of a Non-Orthogonal Cracking Model for Three Dimensions and Six Directions 156\u003c\/p\u003e \u003cp\u003e11.3 Path-Dependent Variables Defining the Non-Orthogonal Crack Group and its Setting 162\u003c\/p\u003e \u003cp\u003e11.4 Verification at the Element Level (Uniform Field) 164\u003c\/p\u003e \u003cp\u003e11.5 Verification at the Member Level (Uniform Stress Field) 166\u003c\/p\u003e \u003cp\u003e11.6 Conclusions 183\u003c\/p\u003e \u003cp\u003eReferences 183\u003c\/p\u003e \u003cp\u003e\u003cb\u003e12 Shear Ductility and Energy Dissipation of Reinforced Concrete Walls 185\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eThomas T. C. Hsu\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e12.1 Introduction 185\u003c\/p\u003e \u003cp\u003e12.2 Shear Theory 185\u003c\/p\u003e \u003cp\u003e12.3 Softened Membrane Model (SMM) 187\u003c\/p\u003e \u003cp\u003e12.4 Conversion of Biaxial Strains to Uniaxial Strains 189\u003c\/p\u003e \u003cp\u003e12.5 Constitutive Model of Concrete in CSMM 190\u003c\/p\u003e \u003cp\u003e12.6 Constitutive Model of Mild Steel Bars in CSMM 194\u003c\/p\u003e \u003cp\u003e12.7 Hysteretic Loops 194\u003c\/p\u003e \u003cp\u003e12.8 Cyclic Shear Ductility and Energy Dissipation 194\u003c\/p\u003e \u003cp\u003e12.9 Framed Shear Walls Under Cyclic Loading 197\u003c\/p\u003e \u003cp\u003e12.10 Earthquake Application 200\u003c\/p\u003e \u003cp\u003e12.11 Conclusions 201\u003c\/p\u003e \u003cp\u003eReferences 202\u003c\/p\u003e \u003cp\u003e\u003cb\u003e13 Behavior of Reinforced Concrete Elements Subjected to Tri-Directional Shear Stresses 203\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eMoheb Labib, Yashar Moslehy, and Ashraf Ayoub\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e13.1 Introduction 203\u003c\/p\u003e \u003cp\u003e13.2 Previous Research Studies on Structures Subjected to a 3D State of Stress 204\u003c\/p\u003e \u003cp\u003e13.3 Modeling of RC Elements under a 3D State of Stress 207\u003c\/p\u003e \u003cp\u003e13.4 The Universal Panel Tester 209\u003c\/p\u003e \u003cp\u003e13.5 Installation of Out-of-Plane Hydraulic Cylinders 210\u003c\/p\u003e \u003cp\u003e13.6 Application of Out-of-Plane Shear in the Universal Panel Tester 211\u003c\/p\u003e \u003cp\u003e13.7 Test Program 213\u003c\/p\u003e \u003cp\u003e13.8 Behavior of Test Panels Under Tri-Directional Shear Loads 216\u003c\/p\u003e \u003cp\u003e13.9 Interaction Surface of Bi-Directional Shear Stresses 222\u003c\/p\u003e \u003cp\u003e13.10 Summary and Conclusions 223\u003c\/p\u003e \u003cp\u003eAcknowledgments 223\u003c\/p\u003e \u003cp\u003eReferences 224\u003c\/p\u003e \u003cp\u003e\u003cb\u003e14 Pre-Stressed Concrete Containment Structural Design in China 227\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eZufeng Xia\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e14.1 Introduction 227\u003c\/p\u003e \u003cp\u003e14.2 Design Improvements of Pre-Stressed Concrete Containment in Chashma Nuclear Power Plant 229\u003c\/p\u003e \u003cp\u003e14.3 Performance Analysis and Experiment Investigation of Third-Generation Containments 230\u003c\/p\u003e \u003cp\u003e14.4 Applications of Other Containment Structures in Domestic Nuclear Power Plants 232\u003c\/p\u003e \u003cp\u003e14.5 Conceptual Design of Spherical Pre-Stressed Concrete Containment Structures 233\u003c\/p\u003e \u003cp\u003e14.6 Conclusions on Pre-Stressed Concrete Containments 234\u003c\/p\u003e \u003cp\u003eReferences 235\u003c\/p\u003e \u003cp\u003e\u003cb\u003e15 Steel Plate Concrete Walls for Containment Structures in Korea: In-Plane Shear Behavior 237\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eSung-Gul Hong, Seung-Joon Lee, and Myung-Jae Lee\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e15.1 Introduction 237\u003c\/p\u003e \u003cp\u003e15.2 Fundamentals 238\u003c\/p\u003e \u003cp\u003e15.3 In-Plane Shear Behavior Models 238\u003c\/p\u003e \u003cp\u003e15.4 Experimental Programs 248\u003c\/p\u003e \u003cp\u003e15.5 Conclusions 257\u003c\/p\u003e \u003cp\u003eReferences 257\u003c\/p\u003e \u003cp\u003e\u003cb\u003e16 Lessons Learned from Kashiwazaki-Kariwa NPP after Niigataken Chuetsu-Oki Earthquake (2007) in View of SSI Effect 259\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eT. Nishikawa, H. Inoue, S. Motohashi, and K. Ebisawa\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e16.1 Introduction 259\u003c\/p\u003e \u003cp\u003e16.2 Outline of the Earthquake, KK-NPP, and Observed Events 260\u003c\/p\u003e \u003cp\u003e16.3 Simulation Analyses of Observation Records 265\u003c\/p\u003e \u003cp\u003e16.4 Parametric Study on Floor Response 271\u003c\/p\u003e \u003cp\u003e16.5 Conclusions 275\u003c\/p\u003e \u003cp\u003eReferences 276\u003c\/p\u003e \u003cp\u003e\u003cb\u003e17 Blast, Shock, and Impact Hazards to Nuclear Structures 277\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eTheodor Krauthammer\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e17.1 Introduction 277\u003c\/p\u003e \u003cp\u003e17.2 Hazard Environments and Loads 279\u003c\/p\u003e \u003cp\u003e17.3 Experimental Observations 281\u003c\/p\u003e \u003cp\u003e17.4 Computational and Experimental Analysis 283\u003c\/p\u003e \u003cp\u003e17.5 Design and Construction 284\u003c\/p\u003e \u003cp\u003e17.6 Summary 285\u003c\/p\u003e \u003cp\u003eReferences 286\u003c\/p\u003e \u003cp\u003e\u003cb\u003e18 History of Shear Design Provisions in the ASME\/ACI Code for Concrete Reactor Vessels and Containments 287\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eRalph G. Oesterle, W. Gene Corley, and Ahmed Elremaily\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e18.1 Introduction 287\u003c\/p\u003e \u003cp\u003e18.2 Background of ASME\/ACI Code 288\u003c\/p\u003e \u003cp\u003e18.3 Tangential Shear Design Provisions 289\u003c\/p\u003e \u003cp\u003e18.4 Peripheral Shear Design Provisions 299\u003c\/p\u003e \u003cp\u003e18.5 Radial Shear Design Provisions 302\u003c\/p\u003e \u003cp\u003e18.6 Summary 304\u003c\/p\u003e \u003cp\u003eReferences 304\u003c\/p\u003e \u003cp\u003e\u003cb\u003e19 US NRC Requirements for Containment Structure Design 307\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eJohn S. Ma, Bret A. Tegeler, and Brian E. Thomas\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e19.1 Introduction 307\u003c\/p\u003e \u003cp\u003e19.2 Seismic Analysis for Containment Structures 307\u003c\/p\u003e \u003cp\u003e19.3 Design of Containment Structure 312\u003c\/p\u003e \u003cp\u003e19.4 Conclusions 316\u003c\/p\u003e \u003cp\u003eDisclaimer 317\u003c\/p\u003e \u003cp\u003eReferences 317\u003c\/p\u003e \u003cp\u003e\u003cb\u003ePart Three COMPUTER SOFTWARE FOR CONTAINMENT STRUCTURES\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e\u003cb\u003e20 FE Program SCS for Analyzing Wall-Type Concrete Structures 321\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eY.L. Mo, Padmanabha Rao Tadepalli, Norman Hoffman, and Thomas T.C. Hsu\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e20.1 Introduction 321\u003c\/p\u003e \u003cp\u003e20.2 Material Scale 323\u003c\/p\u003e \u003cp\u003e20.3 Element Scale 327\u003c\/p\u003e \u003cp\u003e20.4 Structure Scale 330\u003c\/p\u003e \u003cp\u003e20.5 Validation 332\u003c\/p\u003e \u003cp\u003e20.6 Conclusions 340\u003c\/p\u003e \u003cp\u003eReferences 341\u003c\/p\u003e \u003cp\u003e\u003cb\u003e21 Modeling and Analysis of Nuclear Power Plant Structures Using ANATECH-ANACAP Software System 345\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eJoseph Y.R. Rashid, Randy J. James, and Robert S. Dunham\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e21.1 Introduction 345\u003c\/p\u003e \u003cp\u003e21.2 Concrete Constitutive Formulation in ANACAP-U 346\u003c\/p\u003e \u003cp\u003e21.3 Example Applications 352\u003c\/p\u003e \u003cp\u003eReferences 363\u003c\/p\u003e \u003cp\u003e\u003cb\u003e22 SASSI FE Program for Seismic Response Analysis of Nuclear Containment Structures 365\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eMansour Tabatabaie\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e22.1 Introduction 365\u003c\/p\u003e \u003cp\u003e22.2 Methodology 366\u003c\/p\u003e \u003cp\u003e22.3 Summary 385\u003c\/p\u003e \u003cp\u003eAcknowledgments 385\u003c\/p\u003e \u003cp\u003eReferences 385\u003c\/p\u003e \u003cp\u003e\u003cb\u003e23 FE Program LS-DYNA for Analysis of NPP Structures Including Seismic Soil–Structure Interaction 387\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eUshnish Basu\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e23.1 Introduction 387\u003c\/p\u003e \u003cp\u003e23.2 Relevant Strengths of LS-DYNA 388\u003c\/p\u003e \u003cp\u003e23.3 Analysis Framework 389\u003c\/p\u003e \u003cp\u003e23.4 Perfectly Matched Layer (PML) 390\u003c\/p\u003e \u003cp\u003e23.5 Effective Seismic Input (ESI) 392\u003c\/p\u003e \u003cp\u003e23.6 Numerical Results 394\u003c\/p\u003e \u003cp\u003e23.7 Conclusions 395\u003c\/p\u003e \u003cp\u003eReferences 395\u003c\/p\u003e \u003cp\u003e\u003cb\u003e24 FE Program ATENA for Safety Assessment of NPP Containments 397\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eJan Cervenka and Vladimir Cervenka\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e24.1 Introduction 397\u003c\/p\u003e \u003cp\u003e24.2 Material Model for Concrete 397\u003c\/p\u003e \u003cp\u003e24.3 Validation 399\u003c\/p\u003e \u003cp\u003e24.4 Nonlinear Analysis of Containment Structures 400\u003c\/p\u003e \u003cp\u003e24.5 Conclusions 405\u003c\/p\u003e \u003cp\u003eReferences 405\u003c\/p\u003e \u003cp\u003e\u003cb\u003ePart Four Nuclear Waste Storage Facilities\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003e\u003cb\u003e25 Properties of Concrete Required in Nuclear Power Plants 409\u003cbr\u003e \u003c\/b\u003e\u003ci\u003ePatrick Bamonte and Pietro G. Gambarova\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e25.1 Introduction 409\u003c\/p\u003e \u003cp\u003e25.2 Chemical Attack, Freezing-and-Thawing Cycling 412\u003c\/p\u003e \u003cp\u003e25.3 Permeability and Diffusivity 413\u003c\/p\u003e \u003cp\u003e25.4 Radiation-Shielding Capability and Irradiation Effects 415\u003c\/p\u003e \u003cp\u003e25.5 Volume Changes and Creep 417\u003c\/p\u003e \u003cp\u003e25.6 Thermal and Fire Exposure 417\u003c\/p\u003e \u003cp\u003e25.7 Concrete for Waste-Disposal Structures 432\u003c\/p\u003e \u003cp\u003e25.8 Conclusions 434\u003c\/p\u003e \u003cp\u003eAcknowledgments 436\u003c\/p\u003e \u003cp\u003eReferences 436\u003c\/p\u003e \u003cp\u003e\u003cb\u003e26 Concrete under High Temperature 439\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eKaspar Willam, Yunping Xi, and Daniel J. Naus\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e26.1 Introduction 439\u003c\/p\u003e \u003cp\u003e26.2 The Coupling Among Hygro-Thermo-Mechanical Loading 439\u003c\/p\u003e \u003cp\u003e26.3 Modeling Coupling 443\u003c\/p\u003e \u003cp\u003e26.4 Acceleration of Basic Creep of Concrete by Temperature 445\u003c\/p\u003e \u003cp\u003e26.5 Experimental Data 447\u003c\/p\u003e \u003cp\u003e26.6 High Temperature Test Data 449\u003c\/p\u003e \u003cp\u003e26.7 Concrete Strength Data 451\u003c\/p\u003e \u003cp\u003e26.8 Remarks on Temperature Concrete Data 453\u003c\/p\u003e \u003cp\u003e26.9 Thermo-Elastoplastic Concrete Model 454\u003c\/p\u003e \u003cp\u003e26.10 Loss of Bounded Material Response 455\u003c\/p\u003e \u003cp\u003e26.11 Conclusions 456\u003c\/p\u003e \u003cp\u003eReferences 456\u003c\/p\u003e \u003cp\u003e\u003cb\u003e27 Irradiation Effects on Concrete Structures 459\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eOsamu Kontani, Yoshikazu Ichikawa, Akihiro Ishizawa, Masayuki Takizawa, and Osamu Sato\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e27.1 Introduction 459\u003c\/p\u003e \u003cp\u003e27.2 Background 460\u003c\/p\u003e \u003cp\u003e27.3 Microstructures 461\u003c\/p\u003e \u003cp\u003e27.4 Interaction Between Radiation and Materials 463\u003c\/p\u003e \u003cp\u003e27.5 Mechanism of Concrete Deterioration 465\u003c\/p\u003e \u003cp\u003e27.6 Gamma Ray Irradiation Tests 466\u003c\/p\u003e \u003cp\u003e27.7 Conclusions 472\u003c\/p\u003e \u003cp\u003eAcknowledgments 472\u003c\/p\u003e \u003cp\u003eReferences 473\u003c\/p\u003e \u003cp\u003e\u003cb\u003e28 Activities in Support of Continuing the Service of Nuclear Power Plant Safety Related Concrete Structures 475\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eD. J. Naus\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e28.1 Introduction 475\u003c\/p\u003e \u003cp\u003e28.2 Concrete Structures 476\u003c\/p\u003e \u003cp\u003e28.3 In-Service Inspection and Testing Requirments 478\u003c\/p\u003e \u003cp\u003e28.4 Renewal of Operating Licenses 479\u003c\/p\u003e \u003cp\u003e28.5 Operating Experience and Material Performance 481\u003c\/p\u003e \u003cp\u003e28.6 Management of Aging 484\u003c\/p\u003e \u003cp\u003e28.7 Potential Research Topics 490\u003c\/p\u003e \u003cp\u003e28.8 Summary 491\u003c\/p\u003e \u003cp\u003eReferences 491\u003c\/p\u003e \u003cp\u003e\u003cb\u003e29 Spent Nuclear Fuel Final Disposal in Taiwan 497\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eY. C. Peng\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e29.1 Introduction 497\u003c\/p\u003e \u003cp\u003e29.2 Disposal Program 498\u003c\/p\u003e \u003cp\u003e29.3 Operation Organization and Work Delegation 499\u003c\/p\u003e \u003cp\u003e29.4 Nuclear Backend Fund 500\u003c\/p\u003e \u003cp\u003e29.5 2009 Progress Report 500\u003c\/p\u003e \u003cp\u003e29.6 Conclusions 502\u003c\/p\u003e \u003cp\u003eReferences 502\u003c\/p\u003e \u003cp\u003e\u003cb\u003e30 Safety Features of Dry Storage System at Chinshan Nuclear Power Plant 503\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eYuhao Huang\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e30.1 Introduction 503\u003c\/p\u003e \u003cp\u003e30.2 Major Components and Operation Sequence 504\u003c\/p\u003e \u003cp\u003e30.3 Major Safety Features 506\u003c\/p\u003e \u003cp\u003e30.4 Conclusions 516\u003c\/p\u003e \u003cp\u003eReferences 516\u003c\/p\u003e \u003cp\u003e\u003cb\u003e31 Seismic Consequence Modeling for the Yucca Mountain Repository Project 519\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eStanley A. Orrell and Charles Bryan\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e31.1 Introduction 519\u003c\/p\u003e \u003cp\u003e31.2 Description of the Repository 520\u003c\/p\u003e \u003cp\u003e31.3 The Pre-Closure Safety Case 524\u003c\/p\u003e \u003cp\u003e31.4 The Post-Closure Safety Case 528\u003c\/p\u003e \u003cp\u003e31.5 Summary 533\u003c\/p\u003e \u003cp\u003eReferences 533\u003c\/p\u003e \u003cp\u003eIndex 535\u003c\/p\u003e \u003cp\u003e\u003cb\u003eThomas Hsu, University of Houston\u003c\/b\u003e is Moores Professor of Civil Engineering in the department of civil and environmental engineering at the University of Houston. Professor Hsu has been Principal and Co-Principal Investigator on funded projects for over 30 years, and has received project funding amounting to over $3.5 million. He established the University of Houston's Structural Research Laboratory, and his research work has formed the basis for the shear and torsion design provisions in the American concrete Institute Building Code. He has won numerous awards for his teaching and research, and has authored or edited 4 books on reinforced concrete\u003c\/p\u003e \u003cp\u003e\u003cb\u003eJui-Liang Lin, National Center for Research on Earthquake Engineering (NCREE), Taiwan,\u003c\/b\u003e is an associate researcher with NCREE, Taiwan\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChiun-lin Wu, National Center for Research on Earthquake Engineering (NCREE), Taiwan,\u003c\/b\u003e is an associate researcher with NCREE, Taiwan\u003c\/p\u003e \u003cp\u003eDeveloping sufficient energy resources to replace coal, oil, and gas is a global 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.\u003c\/p\u003e \u003cp\u003e\u003ci\u003eInfrastructure Systems for Nuclear Energy\u003c\/i\u003e 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 investigation of containment structures, nuclear waste storage facilities, and applications of commercial\/academic computer software.\u003c\/p\u003e \u003cp\u003eSpecific environments that challenge the behavior of nuclear power plant infrastructure systems, such as earthquake, blast, high temperature, irradiation effects, soil–structure interaction effect, etc., are also discussed.\u003c\/p\u003e \u003cp\u003eKey features:\u003c\/p\u003e \u003cul\u003e \u003cli\u003eIncludes contributions from global experts representing academia and industry\u003c\/li\u003e \u003cli\u003eProvides an overview of the nuclear power industry and nuclear infrastructure systems\u003c\/li\u003e \u003cli\u003ePresents the state-of-the-art as well as the future direction for nuclear civil infrastructure systems\u003c\/li\u003e \u003c\/ul\u003e \u003cp\u003e\u003ci\u003eInfrastructure Systems for Nuclear Energy\u003c\/i\u003e is a comprehensive, up-to-date reference for researchers and practitioners working in this field and for graduate studies in civil and mechanical engineering.\u003c\/p\u003e","brand":"Wiley","offers":[{"title":"Default Title","offer_id":47989424783589,"sku":"NP9781119975854","price":184.95,"currency_code":"USD","in_stock":false}],"thumbnail_url":"\/\/cdn.shopify.com\/s\/files\/1\/1842\/7735\/files\/9781119975854.jpg?v=1761784053","url":"https:\/\/k12savings.com\/products\/infrastructure-systems-for-nuclear-energy-isbn-9781119975854","provider":"K12savings","version":"1.0","type":"link"}