Pressurised water reactors /
This book, part of the JSME Series in Thermal and Nuclear Power, provides an in-depth exploration of pressurized water reactors (PWRs), focusing on their development, safety features, and technological advancements. Edited by Hidehito Mimaki, Yurugi Kanzaki, and Tomofumi Yamamoto, it presents a comp...
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| Formato: | livro eletrônico |
|---|---|
| Idioma: | inglês |
| Publicado em: |
[Amsterdam] :
Elsevier,
2024.
|
| coleção: | JSME series in thermal and nuclear power generation
|
| Assuntos: | |
| Acesso em linha: | ScienceDirect |
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| 020 | |a 9780128235843 |q (electronic bk.) | ||
| 020 | |a 0128235845 |q (electronic bk.) | ||
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| 082 | 0 | 4 | |a 621.4834 |2 23/eng/20240722 |1 https://id.oclc.org/worldcat/ddc/E48cpFg8P3QP3h7gCb3QJVdYFW |
| 245 | 0 | 0 | |a Pressurised water reactors / |c edited by Hidehito Mimaki, Yurugi Kanzaki and Tomofumi Yamamoto. |
| 260 | |a [Amsterdam] : |b Elsevier, |c 2024. | ||
| 300 | |a 1 online resource. | ||
| 490 | 0 | |a JSME series in thermal and nuclear power generation | |
| 505 | 0 | |a Front Cover -- Pressurized Water Reactors -- Copyright Page -- Contents -- List of contributors -- About the editors and authors -- About the editors -- About the authors -- Preface of JSME Series in Thermal and Nuclear Power Generation -- Preface -- Editorial secretariat -- Cooperation -- Abbreviations -- 1 History of pressurized water reactor development in Japan -- Chapter outline -- 1.1 Introduction -- 1.2 Outline of pressurized water reactor -- 1.2.1 General features of nuclear power plant -- 1.2.2 Features of pressurized water reactor -- 1.3 Brief history of nuclear development -- 1.3.1 Early stage of nuclear development -- 1.3.2 Nuclear energy policy -- 1.3.3 Nuclear regulatory policy -- 1.3.4 Nuclear energy in the primary energy supply -- 1.4 Development of pressurized water reactor -- 1.4.1 Early days of pressurized water reactor technology development -- 1.4.2 Introduction and evolution in Japan -- 1.4.3 Improvements and standardization in Japan -- 1.4.3.1 Improving steam generator reliability -- 1.4.3.2 Improving fuel reliability -- 1.4.3.3 Plant design improvement -- 1.4.4 Current status and summary -- 1.5 Nuclear safety and regulations -- 1.5.1 Concept of defense in depth -- 1.5.2 Events to be considered and their responses -- 1.5.3 Identification of important accident sequences and effectiveness evaluation -- 1.5.3.1 Identification of important accident sequences in measures to prevent core damage, and effectiveness evaluation -- 1.5.3.2 Identification of containment failure modes in the measures to prevent containment failure, and effectiveness evalu... -- 1.5.4 Safety goals and subsidiary objectives -- 1.5.5 Evaluation for continuous safety improvement -- References -- Further reading -- 2 Features of a PWR plant -- 2.1 Introduction -- Further reading -- 2.2 Safety design philosophy -- 2.2.1 Outline. | |
| 505 | 8 | |a 2.2.2 Consideration of external events -- 2.2.2.1 Prevention of damage caused by earthquake -- 2.2.2.2 Consideration of other natural phenomena -- 2.2.2.3 Consideration of human-induced events -- 2.2.2.4 Consideration of a combination of natural phenomena -- 2.2.3 Consideration on internal events -- 2.2.3.1 Prevention of damage caused by fire -- 2.2.3.1.1 Prevention of fires -- 2.2.3.1.2 Detection and extinguishment of fire -- 2.2.3.1.3 Mitigation of fire damage -- 2.2.3.2 Prevention of damage caused by flooding or the like -- 2.2.3.3 Prevention of breakage due to an internally generated missile -- 2.2.4 Safety facilities for design basis events -- 2.2.4.1 Facilities related to the reactor -- 2.2.4.1.1 "Shutting down" function -- 2.2.4.1.2 "Cooling" function -- 2.2.4.1.3 "Containment" function -- 2.2.4.2 Facilities related to the handling and storage of fuel assemblies, etc -- 2.2.4.3 Facilities related to the processing and storage of radioactive waste -- 2.2.4.4 Other facilities -- 2.2.4.5 Common facilities -- 2.2.5 Safety facilities for severe accidents -- 2.2.5.1 Measures to prevent the core from being severely damaged -- 2.2.5.1.1 "Shutting down" function -- 2.2.5.1.2 "Cooling" function -- 2.2.5.1.3 "Containment" function -- 2.2.5.2 Measures necessary for the prevention of the containment vessel from being damaged, which is required in the event ... -- 2.2.5.3 Measures for the spent fuel pit -- 2.2.5.4 Measures to suppress radioactive materials dispersion outside the facility -- 2.2.5.5 Other requirements -- 2.2.6 Specialized safety facilities -- 2.2.7 Radiation protection -- 2.2.7.1 Fundamental principle -- 2.2.7.2 Radiological protection of the public -- 2.2.7.3 Protection from occupational radiation exposures -- 2.3 Plant layout -- 2.3.1 Outline -- 2.3.2 Plot plan -- 2.3.2.1 Reactor building and auxiliary building -- 2.3.2.2 Turbine building. | |
| 505 | 8 | |a 2.3.2.3 Switchyard -- 2.3.2.4 Cooling water intake and outlet system -- 2.3.2.5 Access control facility -- 2.3.2.6 Radioactive waste storage building -- 2.3.2.7 Cask storage building -- 2.3.2.8 Water supply and treatment systems -- 2.3.2.9 Safety facilities for severe accidents and specialized safety facilities -- 2.3.2.10 Port facility -- 2.3.3 Layout of systems and components -- 2.3.3.1 Reactor building -- 2.3.3.2 Auxiliary building -- 2.3.3.3 Turbine building -- 2.3.3.4 Fuel handling and storage system -- 2.3.4 Design considerations for plant layout -- 2.3.4.1 Building configuration -- 2.3.4.2 Design considerations for layout -- 2.3.4.2.1 Basic conditions -- 2.3.4.2.2 Functional requirements -- (1) Seismic resistance of the building -- (2) Separation of safety system -- (3) Protection against natural hazards (excluding earthquakes) -- (4) Reduction of radiation exposure -- (5) Others -- 2.3.4.2.3 Other detailed design requirements -- (1) Seismic resistance of the building -- (2) Separation of safety system -- (3) Protection against natural hazards -- (4) Reduction of radiation exposure -- (5) Others -- Further reading -- 2.4 Reactor and core -- 2.4.1 Outline -- 2.4.2 Fuel rod and fuel assembly -- 2.4.2.1 Structure of fuel rods and fuel assemblies -- 2.4.2.1.1 Fuel rod -- 2.4.2.1 2 Fuel assembly -- 2.4.2.2 Fuel rod and fuel assembly design -- 2.4.2.3 Development of M-MDATM Material -- 2.4.3 Reactor and core -- 2.4.3.1 Structure of reactor and core -- 2.4.3.2 Core design -- 2.4.3.2.1 Determination of the core size -- 2.4.3.2.2 Nuclear design required to ensure safety -- (1) Initial core -- (2) Reload core -- 2.4.3.2.3 Thermal-hydraulic design conditions required to ensure safety -- 2.4.3.3 Dynamic characteristics of reactor -- 2.4.3.4 Stability of core -- 2.4.3.4.1 Stability of core characteristics. | |
| 505 | 8 | |a 2.4.3.4.2 Stability of reactor with control systems -- 2.4.3.4.3 Stability of spatial oscillation of xenon -- 2.4.3.5 Reactivity control -- 2.4.3.5.1 Control method and control equipment -- (1) Chemical shim boron -- (2) Control rod -- (3) Burnable poison rod -- 2.4.3.5.2 Startup neutron source -- 2.4.3.6 Power distribution control -- 2.4.3.7 Core management -- 2.4.3.7.1 Basic conditions for reload core design -- 2.4.3.7.2 Concept of reload core design -- 2.4.3.7.3 Power distribution monitoring and burnup management during operation -- 2.4.3.7.4 Fuel integrity management during operation -- 2.4.3.7.5 Fuel inspection during regular inspection -- 2.4.3.7.6 Measures to prevent problems related to fuels -- References -- 2.5 Reactor coolant system -- 2.5.1 Outline -- 2.5.1.1 System configuration -- 2.5.1.2 Function -- (1) Core cooling and heat transfer to the secondary system -- (2) Reactivity control -- (3) Protection of radioactive release -- (4) Pressure control -- 2.5.1.3 Reactor coolant pressure boundary -- 2.5.2 Reactor pressure vessel -- 2.5.2.1 Structure of the reactor vessel -- 2.5.2.2 Reactor vessel design -- 2.5.2.2.1 Materials -- 2.5.2.2.2 Monitoring Irradiation Embrittlement -- 2.5.2.2.3 Stress analysis -- 2.5.2.3 Test and inspection -- 2.5.3 Reactor internals -- 2.5.3.1 Design arrangements -- 2.5.3.2 Functions of reactor internals -- 2.5.3.2.1 Core support and locating -- 2.5.3.2.2 Flow channel formation of reactor coolant and proper flow distribution -- 2.5.3.2.3 Positioning, guide, and protection of the control rods -- 2.5.3.2.4 Guide and protection of instrumentation -- 2.5.3.2.5 Fast neutron fluence protection to the reactor vessel -- 2.5.3.2.6 Limitation of the stroke of the drop in the postulated core drop event -- 2.5.4 Steam generator -- 2.5.4.1 Structure of steam generator -- 2.5.4.2 Steam generator design -- 2.5.4.2.1 Materials. | |
| 505 | 8 | |a 2.5.4.2.2 Stress analysis -- 2.5.4.2.3 Performance -- 2.5.5 Reactor coolant pump -- 2.5.5.1 Hydraulic parts -- 2.5.5.1.1 Casing -- 2.5.5.1.2 Impeller -- 2.5.5.1.3 Turning vane and diffuser assembly -- 2.5.5.1.4 Diffuser adapter -- 2.5.5.2 Thermal barrier and heat exchanger assembly -- 2.5.5.3 Rotor assembly and radial bearing -- 2.5.5.3.1 Rotor assembly -- 2.5.5.3.2 Radial bearing -- 2.5.5.4 Shaft seal -- 2.5.5.4.1 No.1 seal -- 2.5.5.4.2 No.2 seal -- 2.5.5.4.3 No.3 seal -- 2.5.5.4.4 Shutdown seal (option) -- 2.5.5.5 Motor -- 2.5.6 Pressurizer -- 2.5.7 Main coolant pipe -- 2.5.7.1 Structure of main coolant pipe -- 2.5.7.2 Main coolant pipe design -- 2.5.7.2.1 Materials -- 2.5.7.2.2 Pipes -- 2.5.7.2.3 Stress analysis -- 2.5.7.3 Tests and examinations of main coolant pipe -- 2.6 Power conversion system -- 2.6.1 Outline -- 2.6.2 Major systems, components and heat cycle -- 2.6.3 Steam turbine for PWR -- 2.6.3.1 Features of nuclear steam turbine -- 2.6.3.2 Thermal cycling of nuclear turbines -- 2.6.3.3 Structure of nuclear turbine -- 2.6.3.3.1 Overall structure -- 2.6.3.3.2 Rotor -- 2.6.3.3.3 Blade -- 2.6.3.3.4 Casing -- 2.6.3.3.5 Bearing -- 2.6.3.3.6 Main valves -- 2.6.3.3.7 Moisture separator reheater -- 2.6.3.4 Control of nuclear turbines -- 2.6.4 Main steam system -- 2.6.4.1 Main steam safety valve and Main steam relief valve -- 2.6.4.2 Main steam isolation valve and Main steam check valve -- 2.6.4.3 Turbine bypass valve -- 2.6.5 Condensate and feedwater system -- 2.6.5.1 Condenser -- 2.6.5.2 Feedwater heater -- 2.6.5.3 Deaerator -- 2.6.5.4 Gland steam condenser -- 2.6.5.5 Condensate pump -- 2.6.5.6 Feedwater pump -- 2.6.5.7 Condensate polisher -- 2.6.6 Auxiliary feedwater system -- 2.6.6.1 Motor-driven auxiliary feedwater pump -- 2.6.6.2 Turbine-driven auxiliary feedwater pump -- 2.6.6.3 Auxiliary feedwater pit -- 2.6.7 Circulating water system. | |
| 520 | |a This book, part of the JSME Series in Thermal and Nuclear Power, provides an in-depth exploration of pressurized water reactors (PWRs), focusing on their development, safety features, and technological advancements. Edited by Hidehito Mimaki, Yurugi Kanzaki, and Tomofumi Yamamoto, it presents a comprehensive history of PWR development in Japan, detailing nuclear safety regulations and the engineering behind PWR design. It covers the layout and operation of PWR plants, including reactor components, safety measures, and waste management systems. The book also discusses advanced PWR designs and innovations, such as accident-tolerant fuel and seismic design improvements, making it a valuable resource for practitioners, researchers, and students in the field of nuclear engineering. |7 Generated by AI | ||
| 650 | 0 | |a Pressurized water reactors. | |
| 650 | 6 | |a Réacteurs à eau sous pression. |0 (CaQQLa)201-0021204 | |
| 650 | 7 | |a Pressurized water reactors |2 fast |0 (OCoLC)fst01076025 | |
| 776 | 0 | 8 | |i ebook version : |z 9780128235843 |
| 776 | 0 | 8 | |c Original |z 0128235837 |z 9780128235836 |w (OCoLC)1281649652 |
| 856 | 4 | 0 | |3 ScienceDirect |u https://www.sciencedirect.com/science/book/9780128235836 |