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Nuclear Engineering: A Conceptual Introduction to Nuclear Power [Pehme köide]

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(Department of Engineering, Lancaster University, Lancaster, UK)
  • Formaat: Paperback / softback, 420 pages, kõrgus x laius: 235x191 mm, kaal: 910 g
  • Ilmumisaeg: 20-Sep-2017
  • Kirjastus: Butterworth-Heinemann Ltd
  • ISBN-10: 0081009623
  • ISBN-13: 9780081009628
Teised raamatud teemal:
Nuclear Engineering: A Conceptual Introduction to Nuclear PowerSuurem pilt
  • Formaat: Paperback / softback, 420 pages, kõrgus x laius: 235x191 mm, kaal: 910 g
  • Ilmumisaeg: 20-Sep-2017
  • Kirjastus: Butterworth-Heinemann Ltd
  • ISBN-10: 0081009623
  • ISBN-13: 9780081009628
Teised raamatud teemal:
Püsilink: https://www.kriso.ee/db/9780081009628.html
Märksõnad:

Nuclear Engineering: A Conceptual Introduction to Nuclear Power provides coverage of the introductory, salient principles of nuclear engineering in a comprehensive manner for those entering the profession at the end of their degree. The nuclear power industry is undergoing a renaissance because of the desire for low-carbon baseload electricity, the growing population, and environmental concerns about shale gas, so this book is a welcomed addition to the science. In addition, users will find a great deal of information on the change in the industry, along with other topical areas of interest that are uniquely covered.

Intended for undergraduate students or early postgraduate students studying nuclear engineering, this new text will also be appealing to scientifically-literate non-experts wishing to be better informed about the ‘nuclear option'.

  • Presents a succinct and clear explanation of the key facts and concepts on how nuclear engineering power systems function and how their related fuel supply cycles operate
  • Provides full coverage of the nuclear fuel cycle, including its scientific and historical basis
  • Describes a comprehensive range of relevant reactor designs, from those that are defunct, current, and in plan/construction for the future, including SMRs and GenIV
  • Summarizes all major accidents and their impact on the industry and society

Muu info

A concise, relevant, and accessible text for anyone with an interest in the past, present, and future of fission-based nuclear energy production
Chapter 1 Fundamental Concepts
1(18)
1.1 Summary of
Chapter and Learning Objectives
1(1)
1.2 Historical Context: Ernest Rutherford 1871-1937
2(1)
1.3 Introduction
3(1)
1.4 The Nuclear Landscape
3(5)
1.4.1 Atomic Radiation and Nuclear Radiation
3(1)
1.4.2 The Nucleus
4(2)
1.4.3 The Chart of the Nuclides
6(1)
1.4.4 Units of Energy on a Nuclear Scale
7(1)
1.4.5 Nuclear Binding Energy
8(1)
1.5 The Generic Nuclear Reactor
8(7)
1.5.1 Fuel
10(1)
1.5.2 Cladding
11(1)
1.5.3 Coolant
12(1)
1.5.4 Moderator
12(1)
1.5.5 Reactor Circuit
13(2)
1.6 Elementary Nuclear Physics Concepts
15(4)
1.6.1 Conventions for the Expression of Mass
15(1)
1.6.2 Introductory Concepts of Radioactivity
15(1)
Case Studies
16(1)
Revision Guide
17(1)
Problems
18(1)
Chapter 2 Historical Context
19(16)
2.1 Summary of the
Chapter and Learning Objectives
19(1)
2.2 Historical Context: Enrico Fermi 1901-54
20(1)
2.3 Introduction
21(1)
2.4 Natural Reactors
21(2)
2.5 Early Uses of Uranium
23(1)
2.6 The Search for Transuranic Elements and the Discovery of Fission
24(1)
2.7 The Influence of World War II and the Race for the Atomic Bomb
25(1)
2.8 National Trends in Power Reactor Design
26(3)
2.9 The First Reactor: Chicago Pile 1
29(1)
2.10 Advanced Reactors and Alternatives to 235U
30(1)
2.11 Reactor Classification by Generation
31(4)
Revision Guide
33(1)
Problems
34(1)
References
34(1)
Chapter 3 Fundamentals of Radioactivity
35(26)
3.1 Summary of
Chapter and Learning Objectives
35(1)
3.2 Historical Context: Marie Curie 1867-1934
36(1)
3.3 Introduction
36(1)
3.4 The Radioactive Decay Law
37(1)
3.5 Multiple Radioactive Decay Processes and Equilibrium
38(2)
3.6 Radiation Types
40(21)
3.6.1 Photon Radiations: X-Rays and y Rays
40(4)
3.6.2 Heavy Charged Particles: α Decay and α-Particle Radiation
44(4)
3.6.3 β Radiation: Energetic Electrons and Positrons
48(3)
3.6.4 Neutron Radiation
51(4)
Case Studies
55(4)
Revision Guide
59(1)
Problems
59(1)
References
60(1)
Chapter 4 The Fission Process
61(26)
4.1 Summary of
Chapter and Learning Objectives
61(1)
4.2 Historical Context: Lise Meitner 1878-1968
61(1)
4.3 Introduction
62(3)
4.4 Neutron Interactions
65(7)
4.4.1 Definition of Microscopic Cross Section
65(1)
4.4.2 Neutron Interaction Types
66(1)
4.4.3 Neutron Production Parameters
67(1)
4.4.4 The Dependence of Cross-Section With Energy
68(2)
4.4.5 Interaction Rates
70(2)
4.5 Massive Isotopes and the Concept of Binding Energy Per Nucleon
72(2)
4.6 Different Modes of Fission
74(2)
4.7 Neutron Production in Fission
76(4)
4.7.1 Energy
76(1)
4.7.2 Multiplicity
77(3)
4.8 Fission Fragment Characteristics
80(7)
Case Studies
83(2)
Revision Guide
85(1)
Problems
85(1)
References
86(1)
Further Reading
86(1)
Chapter 5 The Actinides and Related Isotopes
87(24)
5.1 Summary of
Chapter and Learning Objectives
87(1)
5.2 Historical Context: Glenn Theodore Seaborg 1912-99
88(1)
5.3 Introduction
88(1)
5.4 The Actinides
89(10)
5.4.1 Common Properties of the Actinide Series of Elements
89(3)
5.4.2 Uranium
92(2)
5.4.3 Plutonium
94(2)
5.4.4 Thorium
96(2)
5.4.5 Curium, Americium and Neptunium
98(1)
5.5 Products of Neutron Activation in Reactors
99(2)
5.5.1 Tritium
99(1)
5.5.2 Sodium-24
100(1)
5.5.3 Cobalt-60
101(1)
5.6 Fission Products
101(5)
5.6.1 Krypton-85
101(1)
5.6.2 Strontium-90
102(1)
5.6.3 Yttrium-90
103(1)
5.6.4 Technetium-99
104(1)
5.6.5 Ruthenium-103 and -106
104(1)
5.6.6 The Iodine Isotopes
105(1)
5.6.7 The Caesium Isotopes
106(1)
5.7 Summary
106(5)
Case Studies
107(1)
Revision Guide
108(1)
Problems
108(1)
References
109(2)
Chapter 6 Moderation
111(18)
6.1 Summary of
Chapter and Learning Objectives
111(1)
6.2 Historical Context: James Chadwick, 1891-1974
111(1)
6.3 Introduction
112(1)
6.4 The Concept of Neutron Economy
113(2)
6.5 Desirable Properties of Moderators
115(14)
6.5.1 Neutron Scattering Interactions Revisited
115(7)
6.5.2 Properties of Specific Moderators
122(2)
Case Studies
124(2)
Revision Guide
126(1)
Problems
126(1)
References
127(2)
Chapter 7 Cooling and Thermal Concepts
129(38)
7.1 Summary of
Chapter and Learning Objectives
129(1)
7.2 Historical Context: Samuel Untermyer II, 1912-2001
130(1)
7.3 Introduction
131(1)
7.4 Fundamental Terminology
132(1)
7.5 Elementary Thermodynamics
133(6)
7.5.1 The Laws of Thermodynamics and the Gas Laws
133(3)
7.5.2 Heat Engines
136(1)
7.5.3 The Carnot Cycle
137(2)
7.5.4 The Rankine Cycle
139(1)
7.6 Properties of Working Substance and Coolants
139(7)
7.6.1 Ideal Requirements
139(3)
7.6.2 Liquid Coolants: Light Water and Heavy Water
142(1)
7.6.3 Gaseous Coolants
143(3)
7.7 Exotic Coolants
146(1)
7.7.1 Sodium
146(1)
7.7.2 Lead
146(1)
7.8 Steam Turbines
147(2)
7.9 Elementary Thermal Hydraulics
149(18)
7.9.1 Thermal Conductivity and the Heat Transfer Coefficient
150(2)
7.9.2 Boiling Heat Transfer
152(4)
7.9.3 Flow
156(3)
7.9.4 Relevance to Accident Scenarios and Safety
159(1)
7.9.5 Current Thermal Hydraulics Challenges
160(1)
Case Studies
161(3)
Revision Guide
164(1)
Problems
165(1)
References
165(2)
Chapter 8 Elementary Reactor Principles
167(38)
8.1 Summary of
Chapter and Learning Objectives
167(1)
8.2 Historical Context: Hyman George Rickover, 1900-86
167(1)
8.3 Introduction
168(1)
8.4 The Domains of Control in Nuclear Reactors
169(1)
8.5 Population Dynamics and Changing Neutron Populations
170(11)
8.5.1 The Multiplication Factor
170(2)
8.5.2 The Neutron Cycle
172(5)
8.5.3 The Significance of Delayed Neutrons
177(4)
8.6 Short-Term Effects and Reactor Feedback Mechanisms
181(8)
8.6.1 Illustrations of Negative and Positive Feedback
181(2)
8.6.2 Some Idiosyncrasies of Criticality Control
183(6)
8.7 Long-Term Effects and Reactor Poisoning
189(16)
8.7.1 The Principle of Poisoning
189(1)
8.7.2 Xenon-135
189(3)
8.7.3 Samarium-149
192(4)
Case Studies
196(5)
Revision Guide
201(1)
Problems
202(1)
References
203(2)
Chapter 9 The Reactor Equation and Introductory Transport Concepts
205(22)
9.1 Summary of
Chapter and Learning Objectives
205(1)
9.2 Historical Context: John von Neumann, 1903-57
206(1)
9.3 Introduction
207(1)
9.4 Relating the Needs of Composition and Geometry in Reactors
207(7)
9.4.1 Neutron Balance and the Diffusion Equation
208(1)
9.4.2 A Conceptual Solution of the Reactor Equation: The Infinite Slab
208(3)
9.4.3 Accounting for Anisotropic Scattering on Light Isotopes
211(2)
9.4.4 The Condition for Criticality
213(1)
9.5 Neutron Transport Mechanisms and Concepts
214(3)
9.5.1 Mechanisms That Influence the Neutron Population in a Small Volume
214(1)
9.5.2 Dependent Variables and the Concept of Phase Space
215(1)
9.5.3 Neutron Density, Vector Flux and Current Density
216(1)
9.6 Development of the One-Group Transport Equation
217(10)
9.6.1 Production
217(1)
9.6.2 Diffusion
217(1)
9.6.3 Scattering in
217(1)
9.6.4 Scattering Out and Absorption Losses
218(1)
Case Studies
218(7)
Revision Guide
225(1)
Problems
225(1)
References
226(1)
Further Reading
226(1)
Chapter 10 Mainstream Power Reactor Systems
227(36)
10.1 Summary of
Chapter and Learning Objectives
227(1)
10.2 Historical Context: Otto Hahn 1879-1968
228(1)
10.3 Introduction
229(1)
10.4 Pressurised Water Reactors
230(13)
10.4.1 Introduction
230(1)
10.4.2 Background to the Use of Light Water
231(2)
10.4.3 Design Overview
233(1)
10.4.4 Reactor Design
234(2)
10.4.5 Thermo-Hydraulic Systems
236(2)
10.4.6 Fuel Design
238(1)
10.4.7 Operation
238(3)
10.4.8 Reactivity Control and Refuelling
241(1)
10.4.9 Protection Systems
241(2)
10.5 Boiling Water Reactors
243(5)
10.5.1 Introduction
243(1)
10.5.2 Design Overview
243(2)
10.5.3 Operation
245(2)
10.5.4 Fuel Design
247(1)
10.5.5 Reactivity Control
247(1)
10.5.6 Protective Systems
248(1)
10.6 Heavy-Water Reactors
248(5)
10.6.1 Introduction
248(1)
10.6.2 Design Overview
249(2)
10.6.3 Operation
251(1)
10.6.4 Fuel Design
251(1)
10.6.5 Control and Protection Systems
251(2)
10.7 Graphite-Moderated, Gas-Cooled Reactors
253(4)
10.7.1 Introduction
253(1)
10.7.2 Background to the Use of Graphite and Carbon Dioxide
254(1)
10.7.3 Design Overview
254(2)
10.7.4 Operation
256(1)
10.7.5 Fuel Design
256(1)
10.7.6 Reactivity Control
257(1)
10.7.7 Protective Systems
257(1)
10.8 Light-Water Graphite Reactors
257(6)
10.8.1 Introduction
257(1)
10.8.2 Design Overview
258(1)
10.8.3 Fuel Design
259(1)
10.8.4 Reactivity Control and Protection
259(1)
10.8.5 Design Modifications After Chernobyl
260(1)
Revision Guide
260(1)
Problems
261(1)
References
261(2)
Chapter 11 Advanced Reactors and Future Concepts
263(34)
11.1 Summary of
Chapter and Learning Objectives
263(1)
11.2 Historical Context: Homi Jehangir Bhabha 1909-66
263(1)
11.3 Introduction
264(1)
11.4 Current Developments: Gen III+ Designs
265(4)
11.4.1 The EPR (European Pressurised Reactor or Evolutionary Power Reactor)
266(1)
11.4.2 The AP1000
267(1)
11.4.3 The Advanced Boiling Water Reactor
268(1)
11.4.4 The APR 1400
268(1)
11.4.5 The Pressurised Heavy Water Reactor
268(1)
11.5 Small Modular Reactors
269(2)
11.5.1 The Uranium Battery (U-Battery)
269(1)
11.5.2 mPower
270(1)
11.5.3 The Westinghouse SMR
271(1)
11.5.4 NuScale™
271(1)
11.6 Breeder Reactors
271(4)
11.7 Generation IV Designs
275(4)
11.7.1 Very High-Temperature Reactor
276(1)
11.7.2 Molten Salt Reactor
276(1)
11.7.3 Sodium-Cooled Fast Reactor
277(1)
11.7.4 Supercritical Water-Cooled Reactor
277(1)
11.7.5 Gas-Cooled Fast Reactor
278(1)
11.7.6 Lead-Cooled Fast Reactor
278(1)
11.8 Thorium
279(3)
11.9 Fusion
282(15)
11.9.1 Background
282(2)
11.9.2 Scientific Basis
284(2)
11.9.3 Engineering Basis
286(3)
Revision Guide
289(1)
Case Studies
289(5)
Problems
294(1)
References
295(2)
Chapter 12 Nuclear Fuel Manufacture
297(10)
12.1 Summary of
Chapter and Learning Objectives
297(1)
12.2 Historical Context: Fritz Strassman 1902-80
297(1)
12.3 Introduction
298(1)
12.4 Mining and Milling
299(1)
12.5 Conversion to Uranium Hexafluoride
300(1)
12.6 Uranium Enrichment
301(1)
12.6.1 The Centrifuge Process
301(1)
12.6.2 Gaseous Diffusion
302(1)
12.6.3 Other Techniques
302(1)
12.7 Nuclear Fuel Manufacture
302(5)
12.7.1 Conversion to Uranium Dioxide
302(1)
12.7.2 Powder Processing and Pellet Manufacture
303(1)
12.7.3 Fuel Pins and Assemblies
303(2)
Revision Guide
305(1)
Problems
305(1)
Reference
305(2)
Chapter 13 Nuclear Fuel Reprocessing
307(16)
13.1 Summary of
Chapter and Learning Objectives
307(1)
13.2 Historical Context: Sir Christopher Hinton 1901-83
307(1)
13.3 Introduction
308(2)
13.4 Nuclear Fuel Reprocessing and Recycling
310(9)
13.4.1 Context
310(1)
13.4.2 Recycling Options
311(1)
13.4.3 Hydrometallurgical Processes: The PUREX Process
312(5)
13.4.4 Pyrochemical Reprocessing
317(2)
13.5 A Summary of Closed Fuel Cycles
319(4)
Revision Guide
320(1)
Problems
321(1)
References
321(1)
Further Reading
321(2)
Chapter 14 Nuclear Safety and Regulation
323(34)
14.1 Summary of the
Chapter and Learning Objectives
323(1)
14.2 Historical Context: Louis Harold Gray 1905-65
323(1)
14.3 Introduction
324(2)
14.4 Radiation Context
326(7)
14.4.1 The Linear No-threshold Model and the Precautionary Principle
326(2)
14.4.2 Radiation Dose
328(3)
14.4.3 Radiotoxicity
331(2)
14.5 Nuclear Accident Classification and Terminology
333(9)
14.5.1 The International Nuclear Event Scale (INES)
333(1)
14.5.2 Accident Types
333(3)
14.5.3 Emergency Core Cooling Systems
336(1)
14.5.4 Prominent Nuclear Incidents
337(5)
14.6 Regulation and Nuclear Safety Philosophies
342(15)
14.6.1 Defence In-depth
342(2)
14.6.2 Regulatory Approaches
344(1)
Example 1 The Nuclear Regulatory Commission (US)
345(1)
Example 2 The Office for Nuclear Regulation (UK)
346(1)
Case Studies
347(6)
Revision Guide
353(1)
Problems
353(1)
References
354(3)
Chapter 15 Radioactive Waste Management and Disposal
357(22)
15.1 Summary of
Chapter and Learning Objectives
357(1)
15.2 Historical Context: Jean-FrEdEric Joliot-Curie 1900-58
358(1)
15.3 Introduction
359(1)
15.4 Radioactive Waste Composition and Timescales of Decay
360(1)
15.5 Radioactive Waste Classifications
361(2)
15.5.1 High Activity Waste
362(1)
15.5.2 Low Level Waste
362(1)
15.5.3 Spent Nuclear Fuel
363(1)
15.5.4 Transuranic Waste (TRU)
363(1)
15.6 Treatment Options for Radioactive Wastes
363(6)
15.6.1 Packaging and Immobilisation
364(2)
15.6.2 Partitioning and Transmutation
366(3)
15.7 Final Disposal Options
369(10)
15.7.1 Deep Geological Disposal
370(2)
15.7.2 Marine Disposal
372(1)
Case Studies
373(3)
Revision Guide
376(1)
Problems
377(1)
References
377(2)
Chapter 16 Public Acceptability, Cost and Nuclear Energy in the Future
379(30)
16.1 Summary of
Chapter and Learning Objectives
379(1)
16.2 Historical Context: Albert Einstein 1879-1955
379(1)
16.3 Introduction
380(1)
16.4 Issues of Public Acceptability and Risk in Nuclear Energy
381(7)
16.4.1 Accidents
381(2)
16.4.2 Siting and Local Communities
383(1)
16.4.3 Intergenerational Equity
384(2)
16.4.4 Radioactive Waste
386(2)
16.5 The Economics of Building Nuclear Power Plant
388(8)
16.5.1 Historical Context
388(1)
16.5.2 Defining the Costs of Nuclear Power Plant
389(3)
16.5.3 Nuclear-Specific Issues
392(2)
16.5.4 The Influence of Long Timescales
394(1)
16.5.5 The Economics of Nuclear Fuel Cycles
395(1)
16.6 Future Options and Nuclear Power
396(13)
16.6.1 Long-Term Future Options and Recent Forecasts
396(3)
16.6.2 As a Source of Low-Carbon Electricity
399(3)
16.6.3 Plans for NPP Worldwide
402(3)
Revision Guide
405(1)
Problems
406(1)
References
406(3)
Index 409
Malcolm Joyce holds a Personal Chair in Nuclear Engineering at Lancaster University and was Head of Department from 2008-2015. His industrial experience includes Smith System Engineering Ltd., BNFL plc. and most recently as Technical Director of Hybrid Instruments Ltd.

His area of research interest is in Nuclear Engineering including nuclear safeguards instrumentation, portable neutron spectrometry,decommissioning-related analytical methods, nuclear policy and environmental consequences, medical radiotherapy & radiation effects. He is author on > 130 refereed journal articles and has specialised over the last 10 years in the field of digital mixed-field radiation assay with fast, organic liquid scintillation detectors. Prior to this he spent four years in research in industry and has a h-index of 26. An impact case study based on Professor Joyce's research submitted to the 2014 Research Excellent Framework was assessed as being of 4* quality.

Professor Joyce was the Scientific Chair of the Nuclear Institute's International Conference on Control & Instrumentation for Nuclear Installations (September 2011). He is a Chartered Engineer and Fellow of the Nuclear Institute. He is Editor on the Elsevier journal Progress in Nuclear Energy. He led the team in 2010 that researched and wrote the Nuclear Lessons Learned report, on behalf of the Royal Academy of Engineering and Engineering the Future. In October 2012, the degree of Doctor of Engineering (DEng) was conferred upon him in recognition of his contribution to the field of Fast Neutron Digitization and Related Analytical Methods. He is a member of the UK Government's Nuclear Industry Research Advisory Board (NIRAB), and elected member of the IEEE Radiation Instrumentation Steering Committee (RISC) and deputy chair of the steering committee of the National Nuclear Users' Facility (NNUF). In 2014 he and his team were awarded the James Watt medal by the Institution of Civil Engineers (ICE) for best paper in the journal Proc. ICE (Energy) for research on the depth profiling of radioactive contamination in concrete.