Cover -- Title Page -- Copyright -- Contents -- List of Contributors -- Preface -- Acronyms -- Chapter 1 Introduction -- 1.1 International Workshop on Infrastructure Systems for Nuclear Energy -- 1.2 Overview of Nuclear Power Plants -- 1.3 Infrastructure for Nuclear Power Industry -- 1.3.1 Technological Infrastructure -- 1.3.2 Regulatory Infrastructure -- 1.3.3 Computer Technology Infrastructure -- 1.3.4 Human Infrastructure -- 1.4 Containment Structures -- 1.4.1 The Pressurized Water Reactors -- 1.4.2 The Boiling Water Reactors -- 1.4.3 Design and Testing Requirements -- 1.5 Nuclear Waste Storage Facilities -- 1.5.1 Spent Fuel Pools -- 1.5.2 Operation -- 1.5.3 Dry Cask Storage -- Part One Infrastructure for Nuclear Power Industry -- Chapter 2 Current Status and Future Role of Nuclear Power -- 2.1 Introduction -- 2.1.1 World Population Aspects -- 2.1.2 World Climate Aspects -- 2.1.3 Contribution of Nuclear Power to the World's Energy Mix and Energy Security -- 2.2 Installed Nuclear Power Capacity in 2011 -- 2.2.1 Power Up-rates of NPPs -- 2.2.2 Operational Issues Caused by Power Up-rates -- 2.2.3 Licensing Aspects for Continued Operation of Current Generation NPPs -- 2.2.4 Nuclear Fuel Supply -- 2.2.5 Radioactive Waste Aspects -- 2.2.6 Operational and Economic Features of NPPs -- 2.2.7 Knowledge Management, Training, and Personnel Requirements -- 2.2.8 Currently Operating Nuclear Power Plant Designs and Status -- 2.2.8.1 Generation I NPPs -- 2.2.8.2 Generation II NPPs -- 2.2.8.3 Generation III and III+ NPPs -- 2.2.8.4 Generation IV -- 2.2.9 Nuclear Fuel Core Damage Frequency (CDF) -- 2.3 Discussion -- 2.4 Conclusions -- 2.5 Further Reading -- References -- Chapter 3 Seismic Probabilistic Risk Assessment for Nuclear Power Plants -- 3.1 Introduction -- 3.2 Conventional SPRA Methodologies.

3.2.1 Seismic Hazard Analysis -- 3.2.2 Component Fragility Evaluation -- 3.2.3 Plant-System and Accident-Sequence Analysis -- 3.2.3.1 Event Trees -- 3.2.3.2 Fault Trees -- 3.2.4 Consequence Analysis -- 3.3 The Methodology of Huang et al. -- 3.3.1 Step 1: Analysis of Plant Systems and Accident Sequences -- 3.3.2 Step 2: Characterization of Seismic Hazard -- 3.3.3 Step 3: Simulation of Structural Responses -- 3.3.4 Step 4: Damage Assessment of NPP Components -- 3.3.5 Step 5: Risk Computation -- 3.4 Summary and Conclusions -- References -- Chapter 4 Seismic Abatement Method for Nuclear Power Plants and Seismic-Isolation Systems for Structural Elements -- 4.1 Main Principles of the Method -- 4.2 Theorem and Proof -- 4.3 Finite Element Construction -- 4.4 Pros and Cons of the Method -- 4.4.1 Advantages of the Method -- 4.4.2 Disadvantages of the Method -- 4.5 Application of the Method to Seismic Isolation Design of Whole Building -- 4.6 Seismic Isolation Devices to Protect Various Elements and Units -- 4.7 Applications -- 4.8 Conclusions -- References -- Chapter 5 Framework for Design of Next-Generation Base-Isolated Nuclear Structures -- 5.1 Introduction -- 5.2 Development of Seismic Isolation Systems -- 5.2.1 Applications of Seismic Isolation -- 5.2.2 Seismic Isolator Units -- 5.3 Seismic Isolation of New Nuclear Power Plant Structures -- 5.3.1 Seismic Isolation Benefits -- 5.3.2 Seismic Isolation Challenges -- 5.4 Performance-Based Design and Evaluation Framework -- 5.4.1 Performance Objectives for a Seismically Isolated Nuclear Power Plant Structure -- 5.4.2 Preliminary Design of the Isolation System -- 5.4.3 Modeling and Evaluation -- 5.5 Conclusions -- References -- Chapter 6 Development of Nuclear Energy in Taiwan -- 6.1 Introduction -- 6.2 Brief Illustration of Nuclear Power Plants.

6.3 Safety of Nuclear Power Generation -- 6.4 Nuclear Safety Enhancement -- 6.5 Radioactive Waste Management -- 6.6 Conclusions -- Chapter 7 Regulatory Challenges on Safety of Nuclear Power Plants in Taiwan -- 7.1 Introduction -- 7.2 Challenge I: New Evidence of Active Faults Near Plants -- 7.2.1 Background -- 7.2.2 Regulatory Status -- 7.2.3 Challenges in the Future -- 7.3 Challenge II: Aging Management -- 7.3.1 Background -- 7.3.2 Regulation of Containment Integrity -- 7.3.3 Regulation of Structure Aging Management -- 7.3.4 Water Seepage in the Torus Area Floor of Chinshan NPP Unit 2 -- 7.3.5 Structure Monitoring Program Issue -- 7.3.6 Challenges in the Future -- 7.4 Challenge III: Risk-Informed In-Service Inspection (RI-ISI) -- 7.4.1 Background and Introduction -- 7.4.2 Regulatory Status -- 7.4.3 Challenges in the Future -- 7.5 Challenge IV-Chinshan Independent Spent Fuel Storage Installation (ISFSI) Program -- 7.5.1 Background of Program -- 7.5.2 Regulatory Control -- 7.5.3 Prospects of Chinshan ISFSI Program -- 7.6 Challenge V: Post-Fukushima Safety Reassessment of NPPs -- 7.6.1 Background of Program -- 7.6.2 Regulatory Status -- 7.6.3 Challenges in the Future -- 7.7 Concluding Remarks -- References -- Chapter 8 Concrete Properties, Safety, and Sustainability of Nuclear Power Plant Infrastructures: New Tools and Themes for Future Research -- 8.1 Introduction -- 8.2 Tools for Design and Analysis: Advanced Damage Modeling -- 8.2.1 Scalar Damage Model (PRM Model) -- 8.2.1.1 Constitutive Relations -- 8.2.1.2 Strain Rate Effects-Internal Friction, Damping -- 8.2.2 Elasto-Plastic Model-PRM Coupled Model -- 8.2.2.1 The Modified Krieg Plasticity Model -- 8.2.2.2 Coupling of Damage and Plasticity Models -- 8.2.2.3 Ability of the Model to Simulate Various Loading Situations.

8.3 Application to Reinforced Concrete Structures -- 8.3.1 Structural Walls Subjected to Earthquake -- 8.3.2 Impact of a Soft Projectile on a Plate -- 8.3.2.1 Test no. 12 -- 8.3.2.2 Test no. 20 -- 8.3.3 Impact on a T-Shape Reinforced Concrete Structure (Hard Shock) -- 8.4 Aging Monitoring -- 8.4.1 Carbonation of Concrete in a Cooling Tower -- 8.4.2 Other Applications of Aging Monitoring -- 8.5 Perspectives and Conclusions -- References -- Chapter 9 Small Modular Reactors: Infrastructure and Other Systems -- 9.1 Introduction -- 9.2 Advantages of SMRs -- 9.3 Regulatory and Technical Issues -- 9.4 Design Features of iPWRs -- 9.5 Conclusions -- Part Two Containment Structures -- Chapter 10 Seismic Design of Reinforced Concrete Structures in Japan: NPP Facilities and High-Rise Buildings -- 10.1 Introduction -- 10.2 Safety Review System of Facilities in Japan -- 10.2.1 Safety Review System for Nuclear Power Plant Facilities -- 10.2.2 Safety Review System for High-Rise Buildings -- 10.3 Design Earthquake Motion for Structures -- 10.3.1 Design Earthquake Motion for Nuclear Power Plant Facilities -- 10.3.2 Design Earthquake Motions for High-Rise Buildings -- 10.4 Modeling of Structures for a Response Analsyis -- 10.4.1 Modeling of NuclearPower Plant Facilities -- 10.4.1.1 Modeling of the BWR and PWR buildings -- 10.4.1.2 Analytical modeling of a BWR building -- 10.4.1.3 Analytical modeling of a PWR building -- 10.4.2 Modeling of High-Rise Buildings -- 10.4.2.1 General remarks -- 10.4.2.2 Modeling of columns, beams/girders, and shear walls -- 10.5 Design Criteria of Structures -- 10.5.1 Design Criteria of Nuclear Power Plant Facilities -- 10.5.2 Design Criteria of High-Rise Building -- 10.6 Concluding Remarks -- References.

Chapter 11 Nonlinear Modeling of 3D Structural Reinforced Concrete and Seismic Performance Assessment -- 11.1 Introduction -- 11.2 Construction of a Non-Orthogonal Cracking Model for Three Dimensions and Six Directions -- 11.3 Path-Dependent Variables Defining the Non-Orthogonal Crack Group and its Setting -- 11.4 Verification at the Element Level (Uniform Field) -- 11.5 Verification at the Member Level (Uniform Stress Field) -- 11.5.1 RC Box and Circular Cylinder Walls Subjected to Multi-Directional Loads -- 11.5.2 Verification by Comparison with Column Member Test Subjected to Flexure and Torsion -- 11.6 Conclusions -- References -- Chapter 12 Shear Ductility and Energy Dissipation of Reinforced Concrete Walls -- 12.1 Introduction -- 12.2 Shear Theory -- 12.2.1 Rotating-Angle Shear Theory -- 12.2.2 Fixed-Angle Shear Theory -- 12.3 Softened Membrane Model (SMM) -- 12.3.1 The Constitutive Relationships of Concrete -- 12.4 Conversion of Biaxial Strains to Uniaxial Strains -- 12.5 Constitutive Model of Concrete in CSMM -- 12.5.1 Softening Coefficient ζ -- 12.5.2 The Function of Deviation Angle f (β) = 1 −

13.6 Application of Out-of-Plane Shear in the Universal Panel Tester.