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. Cover......Page 1 Title Page......Page 5 Copyright......Page 6 Contents......Page 7 List of Contributors......Page 17 Preface......Page 21 Acronyms......Page 23 1.1 International Workshop on Infrastructure Systems for Nuclear Energy......Page 31 1.2 Overview of Nuclear Power Plants......Page 34 1.3 Infrastructure for Nuclear Power Industry......Page 35 1.3.2 Regulatory Infrastructure......Page 36 1.4 Containment Structures......Page 37 1.4.1 The Pressurized Water Reactors......Page 39 1.4.2 The Boiling Water Reactors......Page 40 1.4.3 Design and Testing Requirements......Page 41 1.5.2 Operation......Page 43 1.5.3 Dry Cask Storage......Page 45 Part One Infrastructure for Nuclear Power Industry......Page 47 2.1.2 World Climate Aspects......Page 49 2.1.3 Contribution of Nuclear Power to the World's Energy Mix and Energy Security......Page 50 2.2 Installed Nuclear Power Capacity in 2011......Page 51 2.2.1 Power Up-rates of NPPs......Page 52 2.2.3 Licensing Aspects for Continued Operation of Current Generation NPPs......Page 53 2.2.5 Radioactive Waste Aspects......Page 54 2.2.7 Knowledge Management, Training, and Personnel Requirements......Page 55 2.2.8.2 Generation II NPPs......Page 56 2.2.8.3 Generation III and III+ NPPs......Page 57 2.3 Discussion......Page 58 2.4 Conclusions......Page 60 2.5 Further Reading......Page 61 References......Page 63 3.1 Introduction......Page 65 3.2 Conventional SPRA Methodologies......Page 66 3.2.1 Seismic Hazard Analysis......Page 68 3.2.2 Component Fragility Evaluation......Page 69 3.2.3.1 Event Trees......Page 71 3.2.4 Consequence Analysis......Page 73 3.3 The Methodology of Huang et al.......Page 74 3.3.2 Step 2: Characterization of Seismic Hazard......Page 75 3.3.4 Step 4: Damage Assessment of NPP Components......Page 76 References......Page 78 4.1 Main Principles of the Method......Page 81 4.2 Theorem and Proof......Page 82 4.3 Finite Element Construction......Page 83 4.4.2 Disadvantages of the Method......Page 86 4.5 Application of the Method to Seismic Isolation Design of Whole Building......Page 87 4.6 Seismic Isolation Devices to Protect Various Elements and Units......Page 88 4.7 Applications......Page 89 References......Page 91 5.1 Introduction......Page 93 5.2.1 Applications of Seismic Isolation......Page 95 5.2.2 Seismic Isolator Units......Page 96 5.3.1 Seismic Isolation Benefits......Page 97 5.3.2 Seismic Isolation Challenges......Page 98 5.4.1 Performance Objectives for a Seismically Isolated Nuclear Power Plant Structure......Page 100 5.4.2 Preliminary Design of the Isolation System......Page 101 5.4.3 Modeling and Evaluation......Page 102 5.5 Conclusions......Page 103 References......Page 104 6.1 Introduction......Page 107 6.2 Brief Illustration of Nuclear Power Plants......Page 108 6.3 Safety of Nuclear Power Generation......Page 111 6.5 Radioactive Waste Management......Page 112 6.6 Conclusions......Page 113 7.1 Introduction......Page 115 7.2.1 Background......Page 116 7.2.3 Challenges in the Future......Page 117 7.3.2 Regulation of Containment Integrity......Page 118 7.3.3 Regulation of Structure Aging Management......Page 119 7.3.4 Water Seepage in the Torus Area Floor of Chinshan NPP Unit 2......Page 121 7.4.1 Background and Introduction......Page 122 7.4.2 Regulatory Status......Page 123 7.5.1 Background of Program......Page 124 7.5.2 Regulatory Control......Page 125 7.5.3 Prospects of Chinshan ISFSI Program......Page 127 7.6.2 Regulatory Status......Page 129 7.7 Concluding Remarks......Page 131 References......Page 132 8.1 Introduction......Page 133 8.2.1.1 Constitutive Relations......Page 134 8.2.1.2 Strain Rate Effects-Internal Friction, Damping......Page 136 8.2.2 Elasto-Plastic Model-PRM Coupled Model......Page 137 8.2.2.2 Coupling of Damage and Plasticity Models......Page 138 8.2.2.3 Ability of the Model to Simulate Various Loading Situations......Page 139 8.3 Application to Reinforced Concrete Structures......Page 140 8.3.1 Structural Walls Subjected to Earthquake......Page 141 8.3.2 Impact of a Soft Projectile on a Plate......Page 143 8.3.2.1 Test no. 12......Page 144 8.3.2.2 Test no. 20......Page 146 8.3.3 Impact on a T-Shape Reinforced Concrete Structure (Hard Shock)......Page 147 8.4 Aging Monitoring......Page 149 8.4.1 Carbonation of Concrete in a Cooling Tower......Page 150 8.4.2 Other Applications of Aging Monitoring......Page 152 8.5 Perspectives and Conclusions......Page 153 References......Page 154 9.2 Advantages of SMRs......Page 157 9.4 Design Features of iPWRs......Page 158 9.5 Conclusions......Page 161 Part Two Containment Structures......Page 163 10.2 Safety Review System of Facilities in Japan......Page 165 10.2.2 Safety Review System for High-Rise Buildings......Page 166 10.3.1 Design Earthquake Motion for Nuclear Power Plant Facilities......Page 167 10.3.2 Design Earthquake Motions for High-Rise Buildings......Page 170 10.4.1.2 Analytical modeling of a BWR building......Page 172 10.4.1.3 Analytical modeling of a PWR building......Page 175 10.4.2.1 General remarks......Page 176 10.4.2.2 Modeling of columns, beams/girders, and shear walls......Page 178 10.5.1 Design Criteria of Nuclear Power Plant Facilities......Page 179 10.6 Concluding Remarks......Page 181 References......Page 182 11.1 Introduction......Page 183 11.2 Construction of a Non-Orthogonal Cracking Model for Three Dimensions and Six Directions......Page 186 11.3 Path-Dependent Variables Defining the Non-Orthogonal Crack Group and its Setting......Page 192 11.4 Verification at the Element Level (Uniform Field)......Page 194 11.5.1 RC Box and Circular Cylinder Walls Subjected to Multi-Directional Loads......Page 196 11.5.2 Verification by Comparison with Column Member Test Subjected to Flexure and Torsion......Page 199 References......Page 213 12.2.1 Rotating-Angle Shear Theory......Page 215 12.2.2 Fixed-Angle Shear Theory......Page 216 12.3 Softened Membrane Model (SMM)......Page 217 12.3.1 The Constitutive Relationships of Concrete......Page 218 12.4 Conversion of Biaxial Strains to Uniaxial Strains......Page 219 12.5.2 The Function of Deviation Angle f (β) = 1 − |β|/24◦......Page 220 12.5.3 Damage Coefficient D = 1 − ψ c......Page 223 12.8 Cyclic Shear Ductility and Energy Dissipation......Page 224 12.9 Framed Shear Walls Under Cyclic Loading......Page 227 12.10 Earthquake Application......Page 230 12.11 Conclusions......Page 231 References......Page 232 13.1 Introduction......Page 233 13.2 Previous Research Studies on Structures Subjected to a 3D State of Stress......Page 234 13.3 Modeling of RC Elements under a 3D State of Stress......Page 237 13.4 The Universal Panel Tester......Page 239 13.5 Installation of Out-of-Plane Hydraulic Cylinders......Page 240 13.6 Application of Out-of-Plane Shear in the Universal Panel Tester......Page 241 13.7 Test Program......Page 243 13.8 Behavior of Test Panels Under Tri-Directional Shear Loads......Page 246 13.9 Interaction Surface of Bi-Directional Shear Stresses......Page 252 Acknowledgments......Page 253 References......Page 254 14.1 Introduction......Page 257 14.2.3 Improvements on the Extension Control of Tendons......Page 259 14.3.1 Research Target......Page 260 14.3.2 Research Contents, Division of Labor, and Key Technologies......Page 261 14.4 Applications of Other Containment Structures in Domestic Nuclear Power Plants......Page 262 14.5.2 Framework of Conceptual Design......Page 263 14.6 Conclusions on Pre-Stressed Concrete Containments......Page 264 References......Page 265 15.1 Introduction......Page 267 15.3.1 Overview......Page 268 15.3.2 Modeling of SC Walls with Vertical Ribs......Page 272 15.3.3 Strength Model for SC Walls with Ribs: Orthogonal Net Analogy......Page 274 15.3.4 Strength Model for SC Walls with Ribs: Skew Reinforcement Analogy......Page 275 15.3.5 Deformation Capacity......Page 277 15.4.1 Pure Shear Test......Page 278 15.4.3 Shear Deformation Characteristics......Page 279 15.4.4 Crack Patterns......Page 281 15.4.5 Comparison......Page 282 15.4.6 Shear Wall Tests......Page 283 References......Page 287 16.1 Introduction......Page 289 16.2.2 Outline of KK-NPP......Page 290 16.2.3 Outline of Observed Situation After Earthquake......Page 291 16.3.2 Analytical Models and Conditions......Page 295 16.3.2.3 Modeling of Interaction Between Reactor Building and Surrounding Soil......Page 296 16.3.3 Analysis Method......Page 298 16.3.4.1 Comparison of Floor Response Spectra at Intermediate Floor......Page 300 16.4.2 Effect of Interaction Between Reactor Building and Surrounding Soil......Page 301 16.5 Conclusions......Page 305 References......Page 306 17.1 Introduction......Page 307 17.2 Hazard Environments and Loads......Page 309 17.3 Experimental Observations......Page 311 17.4 Computational and Experimental Analysis......Page 313 17.5 Design and Construction......Page 314 17.6 Summary......Page 315 References......Page 316 18.1 Introduction......Page 317 18.2 Background of ASME/ACI Code......Page 318 18.3.2 US Nuclear Regulatory Research Program......Page 319 18.3.3.2 Strength Provisions......Page 325 18.3.3.4 Further Research......Page 328 18.4.1 Background......Page 329 18.4.2 US Nuclear Regulatory Research Program......Page 330 18.4.3.2 Strength Provisions......Page 331 18.5.1 Background......Page 332 18.5.2.3 Further Research......Page 333 References......Page 334 19.2 Seismic Analysis for Containment Structures......Page 337 19.2.1 Model Development......Page 338 19.2.4 Stiffness Effects......Page 340 19.2.7 Backfill Considerations......Page 341 19.3 Design of Containment Structure......Page 342 19.3.2 Analysis Procedures......Page 343 19.3.6 Metallic Liner Analysis and Design......Page 344 19.3.7 Design Considerations for Grouted Tendons......Page 345 19.4.1 Model Correctness......Page 346 References......Page 347 Part Three Computer Software for Containment Structures......Page 349 20.1 Introduction......Page 351 20.2 Material Scale......Page 353 20.2.1.1 Tension......Page 354 20.2.1.2 Compression......Page 355 20.2.1.4 Pre-stressing Tendons Embedded in Concrete/Steel Fiber Concrete......Page 356 20.3.1 Modeling Cracked Reinforced Concrete......Page 357 20.3.2 Development of Tangent Stiffness Matrix......Page 358 20.4.1 Analysis Procedure......Page 360 20.4.2 OpenSees......Page 361 20.5 Validation......Page 362 20.5.1.1 Analytical Model......Page 363 20.5.1.2 Finite Element Model of Beams......Page 364 20.5.2 Post-Tensioned Pre-Cast Column under Reversed Cyclic Loading......Page 365 20.5.3 Seven-story Reinforced Concrete Wall Building Under Dynamic Loading......Page 367 20.5.3.1 Finite Element Model......Page 368 20.5.3.2 Analysis Procedure......Page 369 20.6 Conclusions......Page 370 References......Page 371 21.1 Introduction......Page 375 21.2 Concrete Constitutive Formulation in ANACAP-U......Page 376 21.2.2 Smeared-Crack Model and Cracking Interaction Curve......Page 377 21.2.3 Post-Cracking Shear Retention and Shear Shedding Model......Page 378 21.2.5 Modeling of Energy Dissipation and Damping Under Dynamic Loading......Page 380 21.3.2 Engineered Missile Impact Tests......Page 382 21.3.3 Airplane Impact on Nuclear Power Plant Structures......Page 386 21.3.3.1 Used-Fuel Pool Subjected to Airplane Impact......Page 388 21.3.3.2 BWR Reinforced Concrete Containment Subjected to Airplane Impact......Page 389 21.3.3.3 Wall Delamination in Pre-Stressed Concrete Containments......Page 391 References......Page 393 22.1 Introduction......Page 395 22.2 Methodology......Page 396 22.2.2 Impedance Analysis......Page 397 22.2.4 Layout of the MTR/SASSI Program......Page 399 22.2.4.2 CNTRL......Page 400 22.2.4.6 ANALYS......Page 401 22.2.4.10 RIMP......Page 402 22.2.4.15 FFIELD......Page 403 22.2.5 MTR/SASSI Analysis of US EPRTM Nuclear Island......Page 404 22.2.5.1 Analysis Results......Page 405 References......Page 415 23.1 Introduction......Page 417 23.2 Relevant Strengths of LS-DYNA......Page 418 23.3 Analysis Framework......Page 419 23.4 Perfectly Matched Layer (PML)......Page 420 23.5 Effective Seismic Input (ESI)......Page 422 23.6 Numerical Results......Page 424 References......Page 425 24.2 Material Model for Concrete......Page 427 24.3 Validation......Page 429 24.4 Nonlinear Analysis of Containment Structures......Page 430 References......Page 435 Part Four Nuclear Waste Storage Facilities......Page 437 25.1 Introduction......Page 439 25.1.2 Physical Mechanisms......Page 441 25.2 Chemical Attack, Freezing-and-Thawing Cycling......Page 442 25.3 Permeability and Diffusivity......Page 443 25.4.1 Radiation-Shielding Capability......Page 445 25.4.2 Irradiation Effects......Page 446 25.6 Thermal and Fire Exposure......Page 447 25.6.2 High-Performance/High-Strength Concrete......Page 450 25.6.4 Light-Weight Concrete......Page 454 25.6.5 Self-Compacting/Consolidating Concrete......Page 456 25.6.6 Shotcrete......Page 457 25.6.7 Spalling......Page 460 25.7 Concrete for Waste-Disposal Structures......Page 462 25.8 Conclusions......Page 464 References......Page 466 26.2 The Coupling Among Hygro-Thermo-Mechanical Loading......Page 469 26.2.1 T-P (Heating and Drying Coupling)......Page 470 26.2.2 U-P (Mechanical Loading and Drying Coupling)......Page 471 26.2.3 U-T (mechanical loading and heating coupling)......Page 472 26.3 Modeling Coupling......Page 473 26.3.2 Load-Induced Thermal Strain (LITS)......Page 474 26.4 Acceleration of Basic Creep of Concrete by Temperature......Page 475 26.5 Experimental Data......Page 477 26.6 High Temperature Test Data......Page 479 26.7 Concrete Strength Data......Page 481 26.8 Remarks on Temperature Concrete Data......Page 483 26.9 Thermo-Elastoplastic Concrete Model......Page 484 26.10 Loss of Bounded Material Response......Page 485 References......Page 486 27.1 Introduction......Page 489 27.2 Background......Page 490 27.3.1 Microstructure of Cement Paste......Page 491 27.3.2 Microstructure of Aggregates......Page 492 27.4.1 Interaction Between Gamma Rays and Materials......Page 493 27.5 Mechanism of Concrete Deterioration......Page 495 27.6.1 Significance of Gamma Ray Irradiation Test......Page 496 27.6.2 Outline of Gamma Ray Irradiation Test......Page 497 27.6.3 Results of Gamma Ray Irradiation Test......Page 498 Acknowledgments......Page 502 References......Page 503 28.1 Introduction......Page 505 28.2.1 Codes and Regulations......Page 506 28.2.2 PWR and BWR Plants......Page 507 28.3 In-Service Inspection and Testing Requirments......Page 508 28.4 Renewal of Operating Licenses......Page 509 28.5.1 Operating Experience......Page 511 28.5.2 Material Performance......Page 512 28.6 Management of Aging......Page 514 28.6.1 Component Selection......Page 515 28.6.2 Aging and Degradation Mechanisms......Page 516 28.6.3 In-Service Inspections......Page 517 28.6.5 Application of Structural Reliability Theory......Page 519 28.7 Potential Research Topics......Page 520 References......Page 521 29.1 Introduction......Page 527 29.2 Disposal Program......Page 528 29.3 Operation Organization and Work Delegation......Page 529 29.5 2009 Progress Report......Page 530 References......Page 532 30.1 Introduction......Page 533 30.2 Major Components and Operation Sequence......Page 534 30.3 Major Safety Features......Page 536 30.3.2 Safety Features: Heat Transfer......Page 537 30.3.3 Safety Feature: Radiation Protection......Page 538 30.3.5.1 Natural Phenomena......Page 539 30.3.5.2 Transient Conditions for Operation and Storage Conditions......Page 540 30.3.5.3 Earthquakes......Page 541 References......Page 546 31.1 Introduction......Page 549 31.2.2 Repository Facilities and Operations......Page 550 31.2.3 Repository Subsurface Design......Page 552 31.3.1 The Probabilistic Seismic Hazard Analysis......Page 554 31.3.2 The Safety Contribution of Engineered Systems, Structures and Components......Page 556 31.4 The Post-Closure Safety Case......Page 558 References......Page 563 Index......Page 565 Supplemental Images......Page 575 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. This book 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 include: 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. -- Edited summary from book