Infrastructure Systems for Nuclear Energy

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