Advanced Nuclear Fuels and Materials
- 1st Edition - February 5, 2025
- Imprint: Elsevier
- Editors: Rongzheng Liu, Malin Liu, Jingtao Ma
- Language: English
- Hardback ISBN:9 7 8 - 0 - 4 4 3 - 2 3 8 1 0 - 9
- eBook ISBN:9 7 8 - 0 - 4 4 3 - 2 3 8 1 1 - 6
Advanced Nuclear Fuels and Materials covers different fuel types such as oxide fuels,metal and alloy fuels, carbide fuels, nitride fuels, composite fuels, and transm… Read more
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Request a sales quoteAdvanced Nuclear Fuels and Materials covers different fuel types such as oxide fuels,
metal and alloy fuels, carbide fuels, nitride fuels, composite fuels, and transmutation
targets. Other fuels discussed include those used in advanced reactor systems, including
high temperature gas cooled reactor fuels, molten salt reactor fuels, sodium cooled fast
reactor fuels, lead cooled fast reactor fuels, gas cooled fast reactor fuels, and supercritical
water reactor fuels.
Additional sections focus on materials used in nuclear reactors, including structural
alloys, control rod materials, and graphite. The numerical simulation of advanced
nuclear fuels, and the frontier of nuclear fuels, including new accident tolerant fuels
and nano materials used in advanced nuclear energy systems are also elaborated.
The comprehensive coverage provided by the book makes it an ideal reference for
senior undergraduates and graduate students and professional researchers/engineers
engaged in nuclear energy, nuclear fuel, or material science.
- The most systematic professional book in the field of nuclear fuel, which comprehensively introduces the current situation of nuclear fuels
- Systematically summarizes the frontier fields of nuclear fuels and nuclear materials keeping readers abreast of the latest progress in scientific research of this area
- Written by senior researchers in the field
Senior undergraduates and graduate students and professional researchers/engineers engaged in nuclear energy, nuclear fuel or material science
- Title of Book
- Cover image
- Title page
- Table of Contents
- Copyright
- Preface
- Brief introduction
- 1. Overview of nuclear energy utilization and materials for nuclear energy
- Abstract
- 1.1 Fundamentals of nuclear energy
- 1.2 Current status of nuclear energy utilization
- 1.3 History of commercial nuclear power plants in the world
- 1.4 Development of commercial reactors
- 1.5 Nuclear fuels and materials
- Bibliography
- 2. Fundamentals of nuclear materials
- Abstract
- 2.1 Overview of the fundamentals of materials science
- 2.2 Basic preparation methods for materials
- 2.3 Material characterization methods
- 2.4 Fundamentals of material irradiation effects
- Bibliography
- Chapter 3. Overview of the nuclear fuel cycle
- Abstract
- 3.1 Nuclear fuel cycle process
- 3.2 Uranium resources and uranium metallurgy
- 3.3 Uranium conversion
- 3.4 Uranium enrichment
- 3.5 Manufacturing of fuel elements (components)
- 3.6 In-reactor use
- 3.7 Reprocessing of nuclear fuel
- Bibliography
- 4. Metal and alloy fuels
- Abstract
- 4.1 Uranium metal
- 4.2 Uranium alloys
- 4.3 Uranium intermetallic compounds
- 4.4 U–Zr–H fuel system
- Bibliography
- 5. Oxide fuels
- Abstract
- 5.1 Properties of uranium dioxide
- 5.2 Preparation of uranium dioxide pellets
- 5.3 Manufacture of uranium dioxide fuel rod
- 5.4 Uranium dioxide fuel assembly in commercial reactor
- 5.5 In-pile irradiation behavior of uranium dioxide fuel rods
- Bibliography
- 6. Non-oxide fuels
- Abstract
- 6.1 Carbide fuel
- 6.2 Nitride fuels
- 6.3 Irradiation effects of nonoxide fuels
- Appendix A
- Bibliography
- 7. Composite fuels and transmutation targets
- Abstract
- 7.1 Composite fuels
- 7.2 Inert matrix fuels
- 7.3 Actinide-containing fuels and transmutation targets
- Bibliography
- 8. High temperature gas-cooled reactor fuels
- Abstract
- 8.1 High-temperature gas-cooled reactor and its development history
- 8.2 High-temperature gas-cooled reactor fuel design
- 8.3 High-temperature gas-cooled reactor fuel element preparation
- 8.4 Forms of failure of high-temperature gas-cooled reactor fuel and in-reactor tests
- 8.5 Research on new nuclear fuel for high-temperature gas-cooled reactors
- Bibliography
- 9. Sodium-cooled fast breeder reactor fuels
- Abstract
- 9.1 Fast neutron reactor and its development history
- 9.2 Principles and operational physical mechanisms of nuclear fuel breeding
- 9.3 Sodium-cooled fast breeder reactor system
- 9.4 Sodium-cooled fast breeder reactor fuel assembly
- 9.5 MOX fuel
- 9.6 In-situ behavior of fast breeder reactor fuel
- 9.7 Development trends of sodium-cooled fast breeder reactor fuel
- Bibliography
- 10. Other fourth-generation reactor fuels
- Abstract
- 10.1 Lead-based liquid metal-cooled reactor fuel
- 10.2 Gas-cooled fast reactor fuel
- 10.3 Supercritical water reactor fuel
- 10.4 Molten salt reactor fuel
- Bibliography
- 11. Functional materials and structural materials for reactors
- Abstract
- 11.1 Reactor control materials
- 11.2 Reactor shielding materials
- 11.3 Material for reflection layer
- 11.4 Reactor structural materials
- Bibliography
- 12. Carbon materials for reactors
- Abstract
- 12.1 Structure of carbon material
- 12.2 Application and development of carbon materials in reactors
- 12.3 Production and microstructure of graphite materials for nuclear use
- 12.4 Properties of graphite materials
- Bibliography
- 13. Materials for fusion reactors
- Abstract
- 13.1 Principal of fusion reactor
- 13.2 Fusion reactor materials
- 13.3 The development of nuclear fusion in China
- Bibliography
- 14. Numerical simulation in advanced nuclear fuels and materials
- Abstract
- 14.1 Introduction to numerical simulation
- 14.2 Numerical simulation classification in advanced nuclear fuels and materials
- 14.3 Examples of practical applications of advanced nuclear fuels and materials simulation
- 14.4 Future development trends of numerical simulation in advanced nuclear fuels and materials
- Bibliography
- 15. Nanostructures and nuclear fuels
- Abstract
- 15.1 Properties of nanomaterials
- 15.2 Nano-nuclear fuels
- 15.3 Nuclear nanostructured materials
- 15.4 Nuclear nanofunctional materials
- Bibliography
- 16. Accident tolerant fuels
- Abstract
- 16.1 Overview of development of accident tolerant fuel
- 16.2 Accident tolerant fuel pellet study
- 16.3 Research on accident tolerant fuel claddings
- 16.4 Development prospect of accident tolerant fuel
- Bibliography
- Index
- Edition: 1
- Published: February 5, 2025
- Imprint: Elsevier
- No. of pages: 540
- Language: English
- Hardback ISBN: 9780443238109
- eBook ISBN: 9780443238116
RL
Rongzheng Liu
Associate Professor, Division of New Materials, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijing, China; from 2021-present is an member of the Editorial Board for the journal Chemical Engineering & Machinery. Research interests include the development and engineering of coated fuel particles for high temperature gas cooled reactor
Affiliations and expertise
Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijing, ChinaML
Malin Liu
Associate Professor, Deputy Head, Division of New Materials, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijing. Visiting Scholar, the Ohio State University, Chemical and Molecular Bioengineering, 2008-2009.
Affiliations and expertise
Associate Professor, Deputy Head, Division of New Materials, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijingc/o our Chinese publishing partner Tsinghua University PressJM
Jingtao Ma
Dr Ma joined Tsinghua University after he received his PhD from the department of Materials in 2003. He has been engaged in the research and development of ceramic materials, particularly nuclear fuel and materials, including those for high temperature gas cooled reactors. He has published about 100peer reviewed papers and has been granted 30 patents.
Affiliations and expertise
Associate Professor, Deputy Head, Division of New Materials, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijingc/o our Chinese publishing partner Tsinghua University PressRead Advanced Nuclear Fuels and Materials on ScienceDirect