Nuclear materials science / Karl Whittle.

Whittle, Karl R. author.
Second edition.
Bristol [England] (Temple Circus, Temple Way, Bristol BS1 6HG, UK) : IOP Publishing, [2020]
IOP ebooks. 2020 collection.
IOP ebooks. [2020 collection]
1 online resource (various pagings) : illustrations (some color).
Nuclear reactors -- Materials.
Nuclear engineering.
Nuclear fuels.
System Details:
Mode of access: World Wide Web.
System requirements: Adobe Acrobat Reader, EPUB reader, or Kindle reader.
Karl received obtained his undergraduate degree at the University of Kent, a masters from the University of Aberdeen, and PhD from the Open University. After completing his PhD he undertook postdoctoral appointments at the Universities of Bristol, Cambridge and Sheffield, researching into amorphous materials, and nuclear waste options. He then moved to the Australia Nuclear Science and Technology Organisation (ANSTO), where he led research into the effects on materials of radiation damage. In 2012 he moved back the UK as Senior Lecturer in Nuclear Materials at the University of Sheffield, and in 2015 he moved to the University of Liverpool as the Chair in Nuclear Engineering. Over the years he has developed research linkages across the world, with active collaborations across the world.
Concerns around climate change and the drive to net-zero carbon energy have led to a nuclear renaissance in many countries. The nuclear industry continues to warn of the increasing need for a highly trained workforce and men and women are needed to perform R&D activities in a range of areas from healthcare and radiation detection to space exploration and advanced materials as well as for the nuclear power industry. Here Karl Whittle provides an overview of the intersection of nuclear engineering and materials science at a level approachable by students from materials, engineering and physics. The text explains the unique aspects needed in the design and implementation of materials for use in demanding nuclear settings. In addition to material properties and their interaction with radiation, the book covers a range of topics including reactor design, fuels, fusion, future technologies and lessons learned from past incidents. Featuring animated figures, this extensively updated and extended edition also includes a new chapter on materials characterisation.
1. Atomic considerations
1.1. Isotopes
1.2. Nuclear stability and radioactive decay
1.3. Alpha-decay ([alpha]-decay)
1.4. Beta-decay ([beta]-decay)
1.5. Beta+/positron emission or electron capture
1.6. Gamma-emission
1.7. How do the mechanisms relate to each other?
1.8. Radioactive half-life
1.9. Decay series
1.10. Observations on isotope stability
1.11. Binding energy
1.12. Fission and fusion
1.13. Spontaneous fission
1.14. Inducing fission and chain reactions
1.15. Neutron absorption, fissile and fertile isotopes
1.16. Increasing fission yield
1.17. What are the key criteria for nuclear fission?
2. Radiation damage
2.1. Key definitions
2.2. Radiation damage
2.3. Prediction of damage
Kinchin-Pease methodology
2.4. Implications of damage
2.5. Outcomes from damage
2.6. Modelling damage build-up in materials
2.7. The bulk effects of damage
3. Nuclear fuel part I
fuel and cladding
3.1. What is required from fuel in a fission reactor?
3.2. Reminder of the fission process
3.3. What are the realistic types of fuel?
3.4. Uranium
3.5. Plutonium
3.6. Fuel containment
3.7. Zirconium-based cladding
3.8. Iron-based cladding
3.9. How do fuel and cladding relate to each other?
4. Nuclear fuel part II
operational effects
4.1. Initial stages
4.2. Classical effects from heating
4.3. Fission products
4.4. Initial reactor operation
4.5. Fuel cladding under operation within the core
4.6. Fuel and cladding
4.7. Cladding corrosion
5. Evolution of reactor technologies
5.1. Generation I
prototype reactors
5.2. GenII
commercial reactors
5.3. GenerationIII/generationIII+
evolved designs
5.4. Molten salt reactors
5.5. Summary
6. The challenge for materials in new reactor designs
6.1. Generation IV
6.2. Reactor types
6.3. Material challenges in GenIV
6.4. Containment
6.5. Radiation damage
6.6. Alternative reactor technology
6.7. Travelling wave reactor
6.8. Thorium reactors
6.9. Small modular reactors
7. The challenges of nuclear waste
7.1. Sources of nuclear waste
7.2. Natural sources of uranium/thorium
7.3. Long-term effects in waste forms
7.4. Long-term behaviour of nuclear waste
7.5. Geological disposal of nuclear waste
7.6. Ceramics and glasses
7.7. Transmutation
8. Materials and nuclear fusion
8.1. Atomic background and recap
8.2. Requirements for fusion
8.3. International Thermonuclear Experimental Reactor
8.4. Outcomes and challenges in fusion
8.5. Material requirements
8.6. Radiation damage and the first wall
8.7. Sputtering
8.8. Gas bubble formation
8.9. The divertor
8.10. Breeding and heat generation
8.11. Tritium breeding
8.12. Challenges in fission and fusion
8.13. Alternative fusion technologies
9. Mistakes made and lessons learnt
9.1. Windscale
9.2. Three Mile Island
9.3. Chernobyl
Reactor 4
9.4. Fukushima Daiichi
9.5. How do the incidents compare?
10. Materials characterisation
10.1. Length scale and characterisation
10.2. X-ray analysis
10.3. X-ray diffraction
10.4. Example applications of x-ray diffraction
10.5. Electron microscopy
10.6. Scanning electron microscopy
10.7. Transmission electron microscopy
10.8. Atom probe tomography (APT).
"Version: 20201101"--Title page verso.
Includes bibliographical references.
Title from PDF title page (viewed on December 4, 2020).
Institute of Physics (Great Britain), publisher.
Other format:
Print version:
Publisher Number:
10.1088/978-0-7503-2376-5 doi
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Restricted for use by site license.
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