Infrastructure Systems for Nuclear Energy
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Thomas Hsu, University of Houston 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
Jui-Liang Lin, National Center for Research on Earthquake Engineering (NCREE), Taiwan, is an associate researcher with NCREE, Taiwan
Chiun-lin Wu, National Center for Research on Earthquake Engineering (NCREE), Taiwan, is an associate researcher with NCREE, Taiwan
Content
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, Bo?idar Stojadinovic, 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
Acronyms
Chapters 10 CFR Title 10 of the Code of Federal Regulations 19 3D Three Dimension 16 A ABWR Advanced Boiling Water Reactor (light-water cooled) 2 ACI American Concrete Institute 18, 19, 28 AEC Atomic Energy Council, Taiwan 7, 29, 30 AFNR Advanced Fast Neutron spectrum Reactor (sodium cooled) 2 AGR Advanced Gas-cooled Reactor (carbon dioxide cooled) 2 AIJ Architectural Institute of Japan 15 ALWR Advanced Light-Water Reactor 2 AMP Aging Managing Programs 2 ANS American Nuclear Society 28 AOS Add-On-Shield 30 ASCE American Society of Civil Engineers 5 ASME American Society of Mechanical Engineers 7, 18, 19, 26, 28 ASP Aging Surveillance Programs 2 B BARC, India Bhabha Atomic Research Centre in India 24 BDBE Beyond Design-Basis Earthquake 5 Breeders-FBRs See FBR 2 BWR Boiling Water Reactor 1, 2, 10, 16, 17, 28 BWRVIP Boiling Water Reactor Vessel and Internals Project 7 C C Celsius 19 CAMUS French Seismic Research Program 8 CANDU CANada Deuterium Uranium (reactor) (heavy water moderated) 2 CCF Common-Cause Failure 2 CDF Core Damage Frequency 2 CEA French Atomic Agency; Also, French Alternative Energies and Atomic Energy Commission 8 CFR Code of Federal Regulations 1, 18, 28, 31 CO2 Carbon Dioxide 2 CONMOD CONcrete containment MODeling and management 28 CPR Chinese (design) Pressurized (light-water cooled) Reactor 2 CRWMS M&O Civilian Radioactive Waste Management Systems, Management and Operating contractor 31 D DBA Design-Basis Accident 17 DBE Design-Basis Earthquake 5, 30 DBGM Design-Basis Ground Motions 31 DID Defense-In-Depth 2 DM Direct Method 22 DNBM Department of Nuclear Backend Management 29 DOD Department of Defense 17 DOE Department of Energy 1, 9, 17, 31 E E/B External Building 10 EACD Earthquake Analysis of Concrete Dams, a computer program developed at the University of California, Berkeley 23 EBS Engineered Barrier System 31 ECCS Emergency Core Cooling Systems 1, 2 EPR European (evolutionary) Pressurized (light-water cooled) Reactor, a third-generation PWR 1, 2, 22 EPRI Electric Power Research Institute 7, 21, 28 EPU Extended Power Up-rate 2 ESBWR Economic Simplified Boiling Water Reactor (light-water cooled) 2 ESI Effective Seismic Input 23 ETH Zurich Eidgenössische Technische Hochschule Zürich, Swiss Federal Institute of Technology, Zurich 24 EUR European Utility Requirements 22 EW East–West 16 F F Fahrenheit 19 FBR Fast (neutron spectrum) Breeder Reactor 2 FE Finite Element 22 FEM Finite Element Method 16 FEP Features, Events, and Processes 29 FSAR Final Safety Analysis Report 30 FTS Free Thermal Strain 26 G GALL Generic Aging Lessons Learned 28 GDC General Design Criteria, or General Design Criterion 1, 18, 19 GE General Electric Company 2 GEH GE-Hitachi nuclear energy co. 2 GEL Green Energy and Environment Research Laboratories 29 GGE Greenhouse Gas Emission 2 GWh GigaWatt-hour (109 W-hour) 2 H HCLPF High-Confidence-Low-Probability of Failure 3, 5 HDB High-Damping rubber Bearing 5 HE High-Explosive 17 HF High-Frequency 19 HLW High-Level Waste 31 I I/C Inner Concrete 10 IAEA International Atomic Energy Agency 1, 2, 28 IED Improvised Explosive Device 17 ILRT Integrated Leakage Rate Test 1 INER Institute of Nuclear Energy Research, Taiwan 29, 30 IPP Independent Power Producers 6 iPWR integrated PWR 9 ISFSI Independent Spent Fuel Storage Installation 30 ISG Interim Staff Guidance used by the Spent Fuel Project Office of US Nuclear Regulatory Commission 19, 22 ITRI Industrial Technology Research Institute 29 ITS Important To Safety 31 ITWI Important To Waste Isolation 31 J JEAG Japan Electric Association Guidelines 5, 15 JMA Japan Meteorological Agency 16 JNES Japan Nuclear Energy Safety Organization 5 JRC Joint Research Centre, European Commission 8 K KEPCO Kansai Electric Power COmpany 10 KEPRI Korea Electric Power Research Institute 15 KK Kashiwazaki-Kariwa NPP 16 KM Knowledge Management 2 KSSC Korean Society of Steel Construction 15 kWh kiloWatt-hour (103 W-hour) 2 L LCS Large-Core Solution 22 LDB Low-Damping rubber Bearing 5 LITS Load-Induced Thermal Strain 26 LLNL Lawrence Livermore National...
