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.

List of Contributors xv Preface xix Acronyms xxi 1 Introduction 1 Thomas T. C. Hsu, Chiun-Lin Wu, and Jui-Liang Lin 1.1 International Workshop on Infrastructure Systems for Nuclear Energy 1 1.2 Overview of Nuclear Power Plants 4 1.3 Infrastructure for Nuclear Power Industry 5 1.4 Containment Structures 7 1.5 Nuclear Waste Storage Facilities 13 Part One Infrastructure for Nuclear Power Industry 2 Current Status and Future Role of Nuclear Power 19 Philip G. Tipping 2.1 Introduction 19 2.2 Installed Nuclear Power Capacity in 2011 21 2.3 Discussion 28 2.4 Conclusions 30 2.5 Further Reading 31 References 33 3 Seismic Probabilistic Risk Assessment for Nuclear Power Plants 35 Yin-Nan Huang and Andrew S. Whittaker 3.1 Introduction 35 3.2 Conventional SPRA Methodologies 36 3.3 The Methodology of Huang et al. 44 3.4 Summary and Conclusions 48 References 48 4 Seismic Abatement Method for Nuclear Power Plants and Seismic-Isolation Systems for Structural Elements 51 Evgeny Kurbatskiy 4.1 Main Principles of the Method 51 4.2 Theorem and Proof 52 4.3 Finite Element Construction 53 4.4 Pros and Cons of the Method 56 4.5 Application of the Method to Seismic Isolation Design of Whole Building 57 4.6 Seismic Isolation Devices to Protect Various Elements and Units 58 4.7 Applications 59 4.8 Conclusions 61 References 61 5 Framework for Design of Next-Generation Base-Isolated Nuclear Structures 63 Eric Keldrauk, Michael Mieler, Božidar Stojadinović, and Per Peterson 5.1 Introduction 63 5.2 Development of Seismic Isolation Systems 65 5.3 Seismic Isolation of New Nuclear Power Plant Structures 67 5.4 Performance-Based Design and Evaluation Framework 70 5.5 Conclusions 73 References 74 6 Development of Nuclear Energy in Taiwan 77 Hwai-Chiung Hsu 6.1 Introduction 77 6.2 Brief Illustration of Nuclear Power Plants 78 6.3 Safety of Nuclear Power Generation 81 6.4 Nuclear Safety Enhancement 82 6.5 Radioactive Waste Management 82 6.6 Conclusions 83 7 Regulatory Challenges on Safety of Nuclear Power Plants in Taiwan 85 Chuen-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 7.1 Introduction 85 7.2 Challenge I: New Evidence of Active Faults Near Plants 86 7.3 Challenge II: Aging Management 88 7.4 Challenge III: Risk-Informed In-Service Inspection (RI-ISI) 92 7.5 Challenge IV – Chinshan Independent Spent Fuel Storage Installation (ISFSI) Program 94 7.6 Challenge V: Post-Fukushima Safety Reassessment of NPPs 99 7.7 Concluding Remarks 101 References 102 8 Concrete Properties, Safety, and Sustainability of Nuclear Power Plant Infrastructures: New Tools and Themes for Future Research 103 Jacky Mazars, Bruno Capra, Alain Rouquand, and Christophe Pontiroli 8.1 Introduction 103 8.2 Tools for Design and Analysis: Advanced Damage Modeling 104 8.3 Application to Reinforced Concrete Structures 110 8.4 Aging Monitoring 119 8.5 Perspectives and Conclusions 123 References 124 9 Small Modular Reactors: Infrastructure and Other Systems 127 David Diamond 9.1 Introduction 127 9.2 Advantages of SMRs 127 9.3 Regulatory and Technical Issues 128 9.4 Design Features of iPWRs 128 9.5 Conclusions 131 Part Two Containment Structures 10 Seismic Design of Reinforced Concrete Structures in Japan: NPP Facilities and High-Rise Buildings 135 Tetsuo Kubo 10.1 Introduction 135 10.2 Safety Review System of Facilities in Japan 135 10.3 Design Earthquake Motion for Structures 137 10.4 Modeling of Structures for a Response Analsyis 142 10.5 Design Criteria of Structures 149 10.6 Concluding Remarks 151 References 152 11 Nonlinear Modeling of 3D Structural Reinforced Concrete and Seismic Performance Assessment 153 Koichi Maekawa and Naoyuki Fukuura 11.1 Introduction 153 11.2 Construction of a Non-Orthogonal Cracking Model for Three Dimensions and Six Directions 156 11.3 Path-Dependent Variables Defining the Non-Orthogonal Crack Group and its Setting 162 11.4 Verification at the Element Level (Uniform Field) 164 11.5 Verification at the Member Level (Uniform Stress Field) 166 11.6 Conclusions 183 References 183 12 Shear Ductility and Energy Dissipation of Reinforced Concrete Walls 185 Thomas T. C. Hsu 12.1 Introduction 185 12.2 Shear Theory 185 12.3 Softened Membrane Model (SMM) 187 12.4 Conversion of Biaxial Strains to Uniaxial Strains 189 12.5 Constitutive Model of Concrete in CSMM 190 12.6 Constitutive Model of Mild Steel Bars in CSMM 194 12.7 Hysteretic Loops 194 12.8 Cyclic Shear Ductility and Energy Dissipation 194 12.9 Framed Shear Walls Under Cyclic Loading 197 12.10 Earthquake Application 200 12.11 Conclusions 201 References 202 13 Behavior of Reinforced Concrete Elements Subjected to Tri-Directional Shear Stresses 203 Moheb Labib, Yashar Moslehy, and Ashraf Ayoub 13.1 Introduction 203 13.2 Previous Research Studies on Structures Subjected to a 3D State of Stress 204 13.3 Modeling of RC Elements under a 3D State of Stress 207 13.4 The Universal Panel Tester 209 13.5 Installation of Out-of-Plane Hydraulic Cylinders 210 13.6 Application of Out-of-Plane Shear in the Universal Panel Tester 211 13.7 Test Program 213 13.8 Behavior of Test Panels Under Tri-Directional Shear Loads 216 13.9 Interaction Surface of Bi-Directional Shear Stresses 222 13.10 Summary and Conclusions 223 Acknowledgments 223 References 224 14 Pre-Stressed Concrete Containment Structural Design in China 227 Zufeng Xia 14.1 Introduction 227 14.2 Design Improvements of Pre-Stressed Concrete Containment in Chashma Nuclear Power Plant 229 14.3 Performance Analysis and Experiment Investigation of Third-Generation Containments 230 14.4 Applications of Other Containment Structures in Domestic Nuclear Power Plants 232 14.5 Conceptual Design of Spherical Pre-Stressed Concrete Containment Structures 233 14.6 Conclusions on Pre-Stressed Concrete Containments 234 References 235 15 Steel Plate Concrete Walls for Containment Structures in Korea: In-Plane Shear Behavior 237 Sung-Gul Hong, Seung-Joon Lee, and Myung-Jae Lee 15.1 Introduction 237 15.2 Fundamentals 238 15.3 In-Plane Shear Behavior Models 238 15.4 Experimental Programs 248 15.5 Conclusions 257 References 257 16 Lessons Learned from Kashiwazaki-Kariwa NPP after Niigataken Chuetsu-Oki Earthquake (2007) in View of SSI Effect 259 T. Nishikawa, H. Inoue, S. Motohashi, and K. Ebisawa 16.1 Introduction 259 16.2 Outline of the Earthquake, KK-NPP, and Observed Events 260 16.3 Simulation Analyses of Observation Records 265 16.4 Parametric Study on Floor Response 271 16.5 Conclusions 275 References 276 17 Blast, Shock, and Impact Hazards to Nuclear Structures 277 Theodor Krauthammer 17.1 Introduction 277 17.2 Hazard Environments and Loads 279 17.3 Experimental Observations 281 17.4 Computational and Experimental Analysis 283 17.5 Design and Construction 284 17.6 Summary 285 References 286 18 History of Shear Design Provisions in the ASME/ACI Code for Concrete Reactor Vessels and Containments 287 Ralph G. Oesterle, W. Gene Corley, and Ahmed Elremaily 18.1 Introduction 287 18.2 Background of ASME/ACI Code 288 18.3 Tangential Shear Design Provisions 289 18.4 Peripheral Shear Design Provisions 299 18.5 Radial Shear Design Provisions 302 18.6 Summary 304 References 304 19 US NRC Requirements for Containment Structure Design 307 John S. Ma, Bret A. Tegeler, and Brian E. Thomas 19.1 Introduction 307 19.2 Seismic Analysis for Containment Structures 307 19.3 Design of Containment Structure 312 19.4 Conclusions 316 Disclaimer 317 References 317 Part Three COMPUTER SOFTWARE FOR CONTAINMENT STRUCTURES 20 FE Program SCS for Analyzing Wall-Type Concrete Structures 321 Y.L. Mo, Padmanabha Rao Tadepalli, Norman Hoffman, and Thomas T.C. Hsu 20.1 Introduction 321 20.2 Material Scale 323 20.3 Element Scale 327 20.4 Structure Scale 330 20.5 Validation 332 20.6 Conclusions 340 References 341 21 Modeling and Analysis of Nuclear Power Plant Structures Using ANATECH-ANACAP Software System 345 Joseph Y.R. Rashid, Randy J. James, and Robert S. Dunham 21.1 Introduction 345 21.2 Concrete Constitutive Formulation in ANACAP-U 346 21.3 Example Applications 352 References 363 22 SASSI FE Program for Seismic Response Analysis of Nuclear Containment Structures 365 Mansour Tabatabaie 22.1 Introduction 365 22.2 Methodology 366 22.3 Summary 385 Acknowledgments 385 References 385 23 FE Program LS-DYNA for Analysis of NPP Structures Including Seismic Soil–Structure Interaction 387 Ushnish Basu 23.1 Introduction 387 23.2 Relevant Strengths of LS-DYNA 388 23.3 Analysis Framework 389 23.4 Perfectly Matched Layer (PML) 390 23.5 Effective Seismic Input (ESI) 392 23.6 Numerical Results 394 23.7 Conclusions 395 References 395 24 FE Program ATENA for Safety Assessment of NPP Containments 397 Jan Cervenka and Vladimir Cervenka 24.1 Introduction 397 24.2 Material Model for Concrete 397 24.3 Validation 399 24.4 Nonlinear Analysis of Containment Structures 400 24.5 Conclusions 405 References 405 Part Four Nuclear Waste Storage Facilities 25 Properties of Concrete Required in Nuclear Power Plants 409 Patrick Bamonte and Pietro G. Gambarova 25.1 Introduction 409 25.2 Chemical Attack, Freezing-and-Thawing Cycling 412 25.3 Permeability and Diffusivity 413 25.4 Radiation-Shielding Capability and Irradiation Effects 415 25.5 Volume Changes and Creep 417 25.6 Thermal and Fire Exposure 417 25.7 Concrete for Waste-Disposal Structures 432 25.8 Conclusions 434 Acknowledgments 436 References 436 26 Concrete under High Temperature 439 Kaspar Willam, Yunping Xi, and Daniel J. Naus 26.1 Introduction 439 26.2 The Coupling Among Hygro-Thermo-Mechanical Loading 439 26.3 Modeling Coupling 443 26.4 Acceleration of Basic Creep of Concrete by Temperature 445 26.5 Experimental Data 447 26.6 High Temperature Test Data 449 26.7 Concrete Strength Data 451 26.8 Remarks on Temperature Concrete Data 453 26.9 Thermo-Elastoplastic Concrete Model 454 26.10 Loss of Bounded Material Response 455 26.11 Conclusions 456 References 456 27 Irradiation Effects on Concrete Structures 459 Osamu Kontani, Yoshikazu Ichikawa, Akihiro Ishizawa, Masayuki Takizawa, and Osamu Sato 27.1 Introduction 459 27.2 Background 460 27.3 Microstructures 461 27.4 Interaction Between Radiation and Materials 463 27.5 Mechanism of Concrete Deterioration 465 27.6 Gamma Ray Irradiation Tests 466 27.7 Conclusions 472 Acknowledgments 472 References 473 28 Activities in Support of Continuing the Service of Nuclear Power Plant Safety Related Concrete Structures 475 D. J. Naus 28.1 Introduction 475 28.2 Concrete Structures 476 28.3 In-Service Inspection and Testing Requirments 478 28.4 Renewal of Operating Licenses 479 28.5 Operating Experience and Material Performance 481 28.6 Management of Aging 484 28.7 Potential Research Topics 490 28.8 Summary 491 References 491 29 Spent Nuclear Fuel Final Disposal in Taiwan 497 Y. C. Peng 29.1 Introduction 497 29.2 Disposal Program 498 29.3 Operation Organization and Work Delegation 499 29.4 Nuclear Backend Fund 500 29.5 2009 Progress Report 500 29.6 Conclusions 502 References 502 30 Safety Features of Dry Storage System at Chinshan Nuclear Power Plant 503 Yuhao Huang 30.1 Introduction 503 30.2 Major Components and Operation Sequence 504 30.3 Major Safety Features 506 30.4 Conclusions 516 References 516 31 Seismic Consequence Modeling for the Yucca Mountain Repository Project 519 Stanley A. Orrell and Charles Bryan 31.1 Introduction 519 31.2 Description of the Repository 520 31.3 The Pre-Closure Safety Case 524 31.4 The Post-Closure Safety Case 528 31.5 Summary 533 References 533 Index 535