Mendeley出力
Nuclear electric power : safety, operation and control aspects / J.B. Knowles
| データ種別 | 電子ブック |
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| 出版者 | (Hoboken, New Jersey : John Wiley & Sons Inc) |
| 出版年 | 2013 |
| 大きさ | 1 online resource |
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| URL | 配架場所 | 巻 次 | 請求記号 | 登録番号 | 状 態 | コメント | ISBN | 刷 年 | 利用注記 | 予約 | 複写取寄 | 指定図書 |
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| URL | 電子ブック |
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621/N16 | 1181000894 |
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9781118660393 |
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禁帯出 一般本 |
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書誌詳細を非表示
| 一般注記 | "Published simultaneously in Canada"--Title page verso Includes bibliographical references and index Glossary -- Principal Nomenclature -- 1. Energy Sources, Grid Compatibility, Economics and the Environment -- Background -- Geothermal Energy -- Hydro-Electricity -- Solar Energy -- Tidal Energy -- Wind Energy -- Fossil-Fired Power Generation -- Nuclear Generation and Reactor Choice -- A Prologue -- 2. Adequacy of Linear Models and Nuclear Reactor Dynamics -- Linear Models, Stability and Nyquist Theorems -- Mathematical Descriptions of a Neutron Population -- Point Model of Neutron Kinetics -- Temperature and Other Operational Feedback Effects -- Reactor Control : Its Stable Period and Re-equilibrium -- 3. Some Power Station and Grid Control Problems -- Steam Drum Water-Level Control -- Flow Stability in Parallel Boiling Channels -- Grid Power Systems and Frequency Control -- Grid Disconnection for a Nuclear Station with Functioning Scram -- 4. Some Aspects of Nuclear Accidents and Their Mitigation -- Reactor Accident Classification by Probabilities -- Hazards from an Atmospheric Release of Fission Products -- Mathematical Risk, Event Trees and Human Attitudes -- The Farmer-Beattie Siting Criterion -- Examples of Potential Severe Accidents in Fast Reactors and PWRs with their Consequences -- 5. Molten Fuel Coolant Interactions : Analyses and Experiments -- A History and a Mixing Analysis -- Coarse Mixtures and Contact Modes in Severe Nuclear Accidents -- Some Physics of a Vapor Film and its Interface -- Heat Transfer from Contiguous Melt -- Heat Transfer at a Liquid-Vapor Interface and the Condensation Coefficient -- Kinetics, Heat Diffusion, a Triggering Simulation and Reactor Safety -- Melt Fragmentation, Heat Transfer, Debris Sizes and MFCI Yield -- Features of the BUBEX Code and an MFTF Simulation -- 6. Primary Containment Integrity and Impact Studies -- Primary Containment Integrity -- The Pi-Theorem, Scale Models and Replicas -- Experimental Impact Facilities -- Computational Techniques and an Aircraft Impact -- 7. Natural Circulation, Passive Safety Systems and Debris-bed Cooling -- Natural Circulation in Nuclear Plant -- Passive Safety Systems for Water Reactors -- Core Debris-bed Cooling in Water Reactors -- Epilogue Description based on print version record HTTP:URL=https://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=670047 Information=EBSCOhost |
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| 著者標目 | *Knowles, J. B 1936- |
| 件 名 | LCSH:Nuclear power plants LCSH:Nuclear reactors -- Safety measures 全ての件名で検索 LCSH:Nuclear reactors -- Control 全ての件名で検索 LCSH:Nuclear energy LCSH:Electric power systems FREE:TECHNOLOGY & ENGINEERING / Mechanical FREE:Electronic books |
| 分 類 | LCC:TK1078 DC23:621.48/3 |
| 書誌ID | EB00004363 |
| ISBN | 9781118660393 |