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American Society of Civil Engineers seismic design criteria for structures, systems, and components in nuclear facilities [[electronic resource] /] / ASCE, SEI, Structural Engineering Institute of the American Society of Civil Engineers
| American Society of Civil Engineers seismic design criteria for structures, systems, and components in nuclear facilities [[electronic resource] /] / ASCE, SEI, Structural Engineering Institute of the American Society of Civil Engineers |
| Pubbl/distr/stampa | Reston, VA, : American Society of Civil Engineers, c2005 |
| Descrizione fisica | 1 online resource (98 p.) |
| Disciplina | 621.48/32 |
| Collana | ASCE standard |
| Soggetto topico |
Nuclear power plants - Earthquake effects
Earthquake resistant design |
| Soggetto genere / forma | Electronic books. |
| ISBN | 0-7844-7113-4 |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
""Contents""; ""List of Figures""; ""List of Tables""; ""Foreword""; ""Acknowledgments""; ""Acronyms/Notation""; ""Definitions""; ""Standard""; ""1.0 Introduction""; ""1.1 Overview of the Seismic Design Criteria""; ""1.2 Use of ASCE Standard 43-05 with Other Codes and Standards""; ""1.3 Alternative Methods to Meet Intent of this Standard""; ""2.0 Earthquake Ground Motion""; ""2.1 Seismic Hazard Evaluation""; ""2.2 Development of DBE Ground Motion""; ""2.3 Method to Define the Design Response Spectra at Various Depths in the Site Profile""
""2.4 Criteria for Developing Synthetic or Modified Recorded Time Histories""""3.0 Evaluation of Seismic Demand""; ""3.1 Introduction""; ""3.2 Linear Analysis""; ""3.3 Nonlinear Analysis""; ""3.4 Modeling and Input Parameters""; ""4.0 Evaluation of Structural Capacity""; ""4.1 Structural Systems""; ""4.2 Structural Capacities""; ""4.3 Deformation and Rotation Capacities""; ""5.0 Load Combinations and Acceptance Criteria for Structures""; ""5.1 Load Combinations""; ""5.2 Acceptance Criteria""; ""6.0 Ductile Detailing Requirements""; ""6.1 Steel Structures""; ""6.2 Reinforced Concrete"" ""6.3 Anchorage""""7.0 Special Considerations""; ""7.1 Rocking and Sliding of Unanchored Rigid Bodies""; ""7.2 Building Sliding and Overturning""; ""7.3 Seismic Separation""; ""7.4 Seismic Design Considerations for Foundation Elements""; ""7.5 Unreinforced Masonry Used as Movable Partitions, Barriers, and Radiation Shielding""; ""7.6 Provisions for Construction Effects""; ""8.0 Equipment and Distribution Systems""; ""8.1 Introduction""; ""8.2 Qualification by Analysis""; ""8.3 Qualification by Testing and Experience Data""; ""9.0 Seismic Quality Provisions"" ""9.1 Design Verification and Independent Peer Review""""9.2 Structural Observation, Inspection, and Testing""; ""9.3 Quality Assurance""; ""Appendix A""; ""A.0 Approximate Methods for Sliding and Rocking of an Unanchored Rigid Body""; ""A.1 Approximate Method for Sliding of an Unanchored Rigid Body""; ""A.2 Approximate Method for Rocking of an Unanchored Rigid Body""; ""Appendix B""; ""B.0 Commentary on and Examples of Approximate Methods for Sliding and Rocking of an Unanchored Rigid Body""; ""B.1 Approximate Method for Sliding of an Unanchored Rigid Body"" ""B.2 Approximate Method for Rocking of an Unanchored Rigid Body""""B.3 Example Problems: Rigid Body Rocking and Sliding""; ""B.3.1 Rigid Body Rocking Example""; ""B.3.2 Rigid Body Sliding Example""; ""References for Appendix B.0""; ""Commentary""; ""C1.0 Introduction""; ""C1.1 Overview of the Seismic Design Criteria""; ""C1.2 Use of ASCE Standard 43-05 with Other Codes and Standards""; ""C1.3 Alternative Methods to Meet Intent of this Standard""; ""References for Section C1.0""; ""C2.0 Earthquake Ground Motion""; ""C2.2 Development of Design Basis Earthquake Ground Motion"" ""C2.3 Method to Define the Design Response Spectra at Various Depths in the Site Profile"" |
| Altri titoli varianti | Seismic design criteria for structures, systems, and components in nuclear facilities |
| Record Nr. | UNINA-9910458856403321 |
| Reston, VA, : American Society of Civil Engineers, c2005 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thermal Design of Nuclear Reactors
| Thermal Design of Nuclear Reactors |
| Autore | Winterton R. H. S |
| Pubbl/distr/stampa | Burlington, : Elsevier Science, 1981 |
| Descrizione fisica | 1 online resource (415 p.) |
| Disciplina |
621.48/32
621.4832 |
| Collana | Pergamon international library of science, technology, engineering, and social studies Thermal design of nuclear reactors |
| Soggetto topico |
Nuclear reactors -- Design and construction
Nuclear reactors - Design and construction Mechanical Engineering Engineering & Applied Sciences Nuclear Engineering |
| ISBN | 1-4831-4524-7 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto |
Cover image; Title page; Table of Contents; Other Titles of Interest; Copyright; Preface; Chapter 1: Summary of Reactor Physics; Publisher Summary; INTRODUCTION; FISSION; NEUTRON FLUX AND REACTION CROSS-SECTIONS; CRITICALITY; MODERATORS; BREEDING; THE MULTIPLICATION CONSTANT; NEUTRON FLUX DISTRIBUTION; PRACTICAL REACTOR SYSTEMS; SUMMARY; Chapter 2: Reactor Systems; Publisher Summary; INTRODUCTION; THE PRESSURIZED WATER REACTOR; THE BOILING WATER REACTOR; THE GAS-COOLED REACTOR-THE AGR; THE SODIUM-COOLED FAST BREEDER REACTOR; Chapter 3: Fuel-Rod Design; Publisher Summary; INTRODUCTION
TEMPERATURE DISTRIBUTION IN A CYLINDRICAL FUEL PELLETAllowance for variations in conductivity and heat generation; Effect of porosity on UO2 thermal conductivity; Measurements of UO2 thermal conductivity; HEAT TRANSFER IN THE GAP BETWEEN FUEL AND CLADDING; HEAT TRANSFER THROUGH CYLINDRICAL CLADDING; FISSION GAS RELEASE; DETAILS OF FUEL ROD CONSTRUCTION; Problems; Chapter 4: Forced-Convection Heat Transfer; Publisher Summary; INTRODUCTION; HEAT-TRANSFER COEFFICIENT AND DIMENSIONAL ANALYSIS; HEAT-TRANSFER CORRELATIONS FOR NON-METALS; LIQUID-METAL HEAT TRANSFER; COMPARISON OF COOLANTS IMPROVEMENT OF HEAT TRANSFER USING FINSIMPROVEMENT OF HEAT TRANSFER BY ROUGHENING THE SURFACE; Problems; Chapter 5: Boiling Heat Transfer; Publisher Summary; INTRODUCTION; NUCLEATION; TYPES OF BOILING; FLOW REGIMES IN FORCED-CONVECTION BOILING; Quality, void fraction and slip ratio; HEAT-TRANSFER CORRELATIONS FOR FLOW BOILING; Film boiling; CRITICAL HEAT-FLUX CORRELATIONS FOR FORCED-CONVECTION BOILING OF WATER; Correlations for bulk boiling; Problems; Chapter 6: Fluid Flow; Publisher Summary; INTRODUCTION; PRESSURE DROP WITH A LIQUID COOLANT; PUMPING POWER PRESSURE DROP WITH A GASEOUS COOLANTPRESSURE DROP WITH A TWO-PHASE MIXTURE; CRITICAL FLOW THROUGH BURST PIPES; Problems; Chapter 7: Safety Analysis; Publisher Summary; INTRODUCTION; TIMESCALES OF THE TRANSIENT FLOW AND HEAT-TRANSFER PROCESSES; THE SOURCES OF HEAT; SIMPLE MODEL FOR CLAD TEMPERATURE DURING TRANSIENT; DISCUSSION OF LOSS OF COOLANT ACCIDENTS; THE PROBABILITY APPROACH TO REACTOR SAFETY; THE SODIUM-COOLED FAST REACTOR; Problems; Chapter 8: Core Thermohydraulic Design; Publisher Summary; INTRODUCTION; MAXIMUM CAN TEMPERATURE IN A COOLANT CHANNEL; The maximum fuel temperature MINIMUM CRITICAL HEAT-FLUX RATIOHOT-CHANNEL FACTORS; GAGS; SUBCHANNEL ANALYSIS; INCREASING HEAT OUTPUT IN GAS-COOLED REACTORS; MAXIMISING STEAM PRODUCTION SUBJECT TO FIXED CRITICAL HEAT FLUX RATIO; Problems; Chapter 9: Steam Cycles; Publisher Summary; INTRODUCTION; THE TEMPERATURE-ENTHALPY DIAGRAM; THE BASIC RANKINE CYCLE; FEED WATER HEATING (REGENERATION); PRACTICAL CYCLES FOR WATER REACTORS; PUMPING POWER AND OTHER LOSSES; RADIOACTIVE STEAM IN THE BWR; CYCLES FOR HIGH-TEMPERATURE REACTORS; NET PLANT EFFICIENCY; COMBINED HEAT AND POWER GENERATION; Problems; Chapter 10: Fusion Reactors Publisher Summary |
| Record Nr. | UNINA-9910148607303321 |
Winterton R. H. S
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| Burlington, : Elsevier Science, 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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