Knowles Nuclear Electric Power

Safety, Operation, and Control Aspects
1. Auflage 2013
ISBN: 978-1-118-82829-8
Verlag: John Wiley & Sons
Format: EPUB
Kopierschutz: Adobe DRM (»Systemvoraussetzungen)

E-Book, Englisch, 232 Seiten, E-Book

Assesses the engineering of renewable sources for commercialpower generation and discusses the safety, operation, and controlaspects of nuclear electric power
From an expert who advised the European Commission and UKgovernment in the aftermath of Three Mile Island and Chernobylcomes a book that contains experienced engineering assessments ofthe options for replacing the existing, aged, fossil-fired powerstations with renewable, gas-fired, or nuclear plants.
From geothermal, solar, and wind to tidal and hydro generation,Nuclear Electric Power: Safety, Operation, and ControlAspects assesses the engineering of renewable sources forcommercial power generation and discusses the important aspects ofthe design, operation, and safety of nuclear stations.
Nuclear Electric Power offers:
* Novel, practical engineering assessments for geothermal, hydro,solar, tidal, and wind generation in terms of the available data oncost, safety, environmental damage, capacity factor reliability,and grid compatibility, with some nuclear comparisons
* Eigenvalues and real frequency response functions to assess thestabilities of reactor power, two-phase channel flow, and a Gridnetwork
* A non-linear control strategy with simulation results for aDesign Base Accident scenario
* Original analyses with experimental validation of molten fuelcoolant interactions and aircraft impacts on rigid structures
* Analysis of the circumstances that led to the Fukushimadisaster
Nuclear Electric Power is an important book for allinternational nuclear power agencies and those who work within thefield.

Autoren/Hrsg.

Knowles, J. Brian

Inhaltsverzeichnis

Preface ix
Glossary xiii
Principal Nomenclature xv
1. Energy Sources, Grid Compatibility, Economics, and theEnvironment 1
1.1 Background 1
1.2 Geothermal Energy 3
1.3 Hydroelectricity 5
1.4 Solar Energy 7
1.5 Tidal Energy 8
1.6 Wind Energy 13
1.7 Fossil-Fired Power Generation 17
1.8 Nuclear Generation and Reactor Choice 20
1.9 A Prologue 30
2. Adequacy of Linear Models and Nuclear Reactor Dynamics34
2.1 Linear Models, Stability, and Nyquist Theorems 34
2.2 Mathematical Descriptions of a Neutron Population 44
2.3 A Point Model of Reactor Kinetics 45
2.4 Temperature and Other Operational Feedback Effects 49
2.5 Reactor Control, its Stable Period and Re-equilibrium 51
3. Some Power Station and Grid Control Problems 56
3.1 Steam Drum Water-Level Control 56
3.2 Flow Stability in Parallel Boiling Channels 59
3.3 Grid Power Systems and Frequency Control 63
3.4 Grid Disconnection for a Nuclear Station with Functioning"Scram" 71
4. Some Aspects of Nuclear Accidents and Their Mitigation79
4.1 Reactor Accident Classification by Probabilities 79
4.2 Hazards from an Atmospheric Release of Fission Products82
4.3 Mathematical Risk, Event Trees, and Human Attitudes 84
4.4 The Farmer-Beattie Siting Criterion 87
4.5 Examples of Potential Severe Accidents in Fast Reactors andPWRs with their Consequences 93
5. Molten Fuel Coolant Interactions: Analyses and Experiments101
5.1 A History and a Mixing Analysis 101
5.2 Coarse Mixtures and Contact Modes in Severe NuclearAccidents 105
5.3 Some Physics of a Vapor Film and its Interface 110
5.4 Heat Transfer from Contiguous Melt 115
5.5 Mass Transfer at a Liquid-Vapor Interface and theCondensation Coefficient 121
5.6 Kinetics, Heat Diffusion, a Triggering Simulation, andReactor Safety 124
5.7 Melt Fragmentation, Heat Transfer, Debris Sizes, and MFCIYield 131
5.8 Features of the Bubex Code and an MFTF Simulation 140
6. Primary Containment Integrity and Impact Studies148
6.1 Primary Containment Integrity 148
6.2 The Pi-Theorem, Scale Models, and Replicas 155
6.3 Experimental Impact Facilities 160
6.4 Computational Techniques and an Aircraft Impact 165
7. Natural Circulation, Passive Safety Systems, andDebris-Bed Cooling 173
7.1 Natural Convection in Nuclear Plants 173
7.2 Passive Safety Systems for Water Reactors 179
7.3 Core Debris-Bed Cooling in Water Reactors 181
7.4 An Epilogue 186
References 192
Index 207

Über Autor(innen)

J. Brian Knowles, PhD, DSc, now retired, remainsprofessionally active with CEN Grenoble and KfK, where he compiledthe results of European-wide MFCI experiments. In 1993, he visitedthe Russian Federation to discuss fast reactor collaboration aspart of the European Commission's Whole Core Accident Committee andwas later a member of the OECD-CSNI working group on water reactoraccident management. Dr. Knowles was also a UKAEA Section Head ofThermal Dynamics at Winfrith, where he was responsible for acomprehensive modular simulation of intact plant dynamics used inAGR and proposed fast reactor designs.