Infrastructure systems for nuclear energy / / editors Thomas T. Hsu, Jui-Liang Lin, Chiun-lin Wu |
Pubbl/distr/stampa | Chichester, England : , : Wiley, , 2014 |
Descrizione fisica | 1 online resource (590 p.) |
Disciplina | 621.48 |
Altri autori (Persone) |
HsuThomas T. C <1933-> (Thomas Tseng Chuang)
LinJui-Liang WuChiun-lin |
Soggetto topico |
Nuclear power plants - Earthquake effects
Reinforced concrete construction - Design and construction Nuclear power plants - Design and construction Nuclear power plants - Asia Nuclear facilities - Earthquake effects |
ISBN |
1-118-53625-8
1-118-53626-6 1-118-53627-4 |
Classificazione | TEC009020 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
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 Pools1.5.2 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 NPPs2.2.7 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 Evaluation3.2.3 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 Method4.2 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 |
Record Nr. | UNINA-9910140185003321 |
Chichester, England : , : Wiley, , 2014 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
Infrastructure systems for nuclear energy / / editors Thomas T. Hsu, Jui-Liang Lin, Chiun-lin Wu |
Pubbl/distr/stampa | Chichester, England : , : Wiley, , 2014 |
Descrizione fisica | 1 online resource (590 p.) |
Disciplina | 621.48 |
Altri autori (Persone) |
HsuThomas T. C <1933-> (Thomas Tseng Chuang)
LinJui-Liang WuChiun-lin |
Soggetto topico |
Nuclear power plants - Earthquake effects
Reinforced concrete construction - Design and construction Nuclear power plants - Design and construction Nuclear power plants - Asia Nuclear facilities - Earthquake effects |
ISBN |
1-118-53625-8
1-118-53626-6 1-118-53627-4 |
Classificazione | TEC009020 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto |
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 Pools1.5.2 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 NPPs2.2.7 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 Evaluation3.2.3 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 Method4.2 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 |
Record Nr. | UNINA-9910821296303321 |
Chichester, England : , : Wiley, , 2014 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|