서지주요정보
Nuclear materials science
서명 / 저자 Nuclear materials science / Karl Whittle.
저자명 Whittle, Karl R., author.
단체명 Institute of Physics (Great Britain), publisher.
발행사항 Bristol [England] (Temple Circus, Temple Way, Bristol BS1 6HG, UK) : IOP Publishing, [2020]
Online Access https://iopscience.iop.org/book/978-0-7503-2376-5 URL

서지기타정보

서지기타정보
청구기호 TK9185 .W556 2020eb
판사항 Second edition.
형태사항 1 online resource (various pagings) : illustrations (some color).
총서명 IOP ebooks. [2020 collection]
언어 English
일반주기 "Version: 20201101"--Title page verso.
서지주기 Includes bibliographical references.
내용 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--genesis -- 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--comparison -- 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--Pile-1 -- 9.2. Three Mile Island--Reactor-2 -- 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).
주제 Nuclear reactors --Materials.
Nuclear engineering.
Nuclear fuels.
Materials science. --bicssc
TECHNOLOGY & ENGINEERING / Materials Science / General. --bisacsh
보유판 및 특별호 저록 Print version: 9780750323741 9780750323772
ISBN 9780750323765, 9780750323758, 9780750323741, 9780750323772
기타 표준번호 10.1088/978-0-7503-2376-5
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