IEEE Std 1527-2018 (Revision of IEEE Std 1527-2006) - Redline : IEEE recommended practice for the design of buswork located in seismically active areas - redline / / Institute of Electrical and Electronics Engineers |
Pubbl/distr/stampa | New York, New York : , : IEEE, , 2018 |
Descrizione fisica | 1 online resource |
Disciplina | 621.48 |
Collana | IEEE Std |
Soggetto topico |
Nuclear power plants - Earthquake effects
Earthquake resistant design |
ISBN | 1-5044-5792-7 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | IEEE Std 1527-2018 |
Record Nr. | UNISA-996577946003316 |
New York, New York : , : IEEE, , 2018 | ||
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Lo trovi qui: Univ. di Salerno | ||
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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 | ||
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Lo trovi qui: Univ. Federico II | ||
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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 | ||
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Lo trovi qui: Univ. Federico II | ||
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Recommendations for revision of seismic damping values in Regulatory guide 1.61 [[electronic resource] /] / prepared by R.J. Morante |
Autore | Morante R. J |
Pubbl/distr/stampa | Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 |
Descrizione fisica | xvi, 32 pages : digital, PDF file |
Soggetto topico |
Nuclear power plants - Earthquake effects
Earthquake resistant design Damping (Mechanics) |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910697849103321 |
Morante R. J
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Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 | ||
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Lo trovi qui: Univ. Federico II | ||
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A review of the Limerick Generating Station severe accident risk assessment : review of core-melt frequency / / prepared by M.A. Azarm [and nine others] |
Autore | Azarm M. |
Pubbl/distr/stampa | Washington, D.C. : , : Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , 1984 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Soggetto topico |
Nuclear power plants - Inspection - United States
Nuclear power plants - Earthquake effects |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Review of the Limerick Generating Station severe accident risk assessment |
Record Nr. | UNINA-9910706520303321 |
Azarm M.
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Washington, D.C. : , : Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , 1984 | ||
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Lo trovi qui: Univ. Federico II | ||
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Seismic design criteria for structures, systems, and components in nuclear facilities / / American Society of Civil Engineers |
Pubbl/distr/stampa | Reston, Virginia : , : American Society of Civil Engineers, , [2019] |
Descrizione fisica | 1 online resource (107 pages) : illustrations |
Disciplina | 621.4832 |
Collana | ASCE standard |
Soggetto topico | Nuclear power plants - Earthquake effects |
Soggetto genere / forma | Electronic books. |
ISBN | 0-7844-8240-3 |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910449761803321 |
Reston, Virginia : , : American Society of Civil Engineers, , [2019] | ||
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Lo trovi qui: Univ. Federico II | ||
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Seismic failure and cask drop analyses of the spent fuel pools at two representative nuclear power plants / / prepared by P. G. Prassinos [and eight others] |
Autore | Prassinos P. G. |
Pubbl/distr/stampa | Washington, D.C. : , : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 1989 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Soggetto topico |
Spent reactor fuels - Storage - Safety measures
Nuclear power plants - Earthquake effects Nuclear fuel rods - Accidents |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910706823803321 |
Prassinos P. G.
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Washington, D.C. : , : Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 1989 | ||
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Lo trovi qui: Univ. Federico II | ||
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Seismic margin review of the Maine Yankee Atomic Power Station |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 1987 |
Descrizione fisica | 1 online resource (3 volumes) : illustrations |
Soggetto topico |
Nuclear power plants - Earthquake effects - Maine
Nuclear power plants - Maine - Design and construction Earthquake resistant design - Maine Earthquake resistant design Nuclear power plants - Design and construction Nuclear power plants - Earthquake effects |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto | Vol. 1. Summary report / prepared by P.G. Prassinos, R.C. Murray, G.E. Cummings -- vol. 2. Systems analysis / prepared by D.L. Moore [and three others] -- vol. 3. Fragility analysis / prepared by M.K. Ravindra [and three others]. |
Record Nr. | UNINA-9910706736903321 |
Washington, DC : , : Division of Engineering Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 1987 | ||
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Lo trovi qui: Univ. Federico II | ||
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Seismic qualification of auxiliary feedwater systems |
Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1981 |
Descrizione fisica | 1 online resource |
Collana | Generic letter |
Soggetto topico |
Feed-water
Nuclear power plants - Earthquake effects Nuclear power plants - Safety measures |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910715916503321 |
Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1981 | ||
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Lo trovi qui: Univ. Federico II | ||
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Seismic qualification of auxiliary feedwater systems |
Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1980 |
Descrizione fisica | 1 online resource |
Collana | Generic letter |
Soggetto topico |
Nuclear power plants - Earthquake effects
Nuclear power plants - Safety measures Feed-water |
Formato | Materiale a stampa ![]() |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910715933303321 |
Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1980 | ||
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Lo trovi qui: Univ. Federico II | ||
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