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Advanced nuclear fuels and materials /

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Advanced 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 f...

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Bibliographic Details
Main Authors: Liu, Rongzheng (Author), Liu, Malin (Author), Ma, Jingtao (Author)
Corporate Author: Knovel (Firm)
Format: eBook
Language:English
Published: Amsterdam : Elsevier, 2025.
Subjects:
Nuclear fuels.
Combustibles nucléaires.
Electronic books.
Online Access:Connect to the full text of this electronic book
Table of Contents:
  • Front Cover
  • Advanced Nuclear Fuels and Materials
  • Copyright Page
  • Contents
  • Preface
  • Brief introduction
  • 1 Overview of nuclear energy utilization and materials for nuclear energy
  • 1.1 Fundamentals of nuclear energy
  • 1.1.1 Nuclear reactions
  • 1.1.2 Neutron cross-sections
  • 1.1.3 Neutron moderation
  • 1.1.4 Nuclear fission and decay
  • 1.2 Current status of nuclear energy utilization
  • 1.2.1 Fission reactors
  • 1.2.2 Nuclear weapons
  • 1.2.2.1 Atomic bombs
  • 1.2.2.2 Hydrogen bombs
  • 1.2.2.3 Neutron bombs
  • 1.2.3 Nuclear power plants
  • 1.2.3.1 Nuclear-powered aircraft carriers
  • 1.2.3.2 Nuclear submarines
  • 1.2.3.3 Nuclear-powered merchant ships
  • 1.2.3.4 Nuclear-powered rockets
  • 1.2.3.5 Nuclear-powered satellites
  • 1.3 History of commercial nuclear power plants in the world
  • 1.3.1 History of nuclear power development
  • 1.3.1.1 Initial period (1954-65)
  • 1.3.1.2 Outbreak period (1966-80)
  • 1.3.1.3 Low tide period (1981-2000)
  • 1.3.1.4 Recovery period (2001-present)
  • 1.3.2 Current status of nuclear power development in the world
  • 1.3.3 Current status of nuclear power development in China
  • 1.4 Development of commercial reactors
  • 1.4.1 Types of commercial reactors
  • 1.4.1.1 Pressurized light water moderated and cooled reactor
  • 1.4.1.2 Boiling water cooled and moderated reactor
  • 1.4.1.3 Pressurized heavy water moderated and cooled reactor
  • 1.4.2 History of commercial reactor development
  • 1.4.2.1 First-generation nuclear power plant
  • 1.4.2.2 Second-generation nuclear power plant
  • 1.4.2.3 Third-generation nuclear power plants
  • 1.4.2.4 Fourth-generation nuclear energy system
  • 1.4.3 Other advanced nuclear energy systems
  • 1.4.3.1 Traveling wave reactors
  • 1.4.3.2 Accelerator-driven nuclear energy systems
  • 1.4.3.3 Fusion reactors
  • 1.5 Nuclear fuels and materials
  • 1.5.1 Nuclear fuels.
  • 1.5.2 Nuclear materials
  • 1.5.2.1 Cladding materials
  • 1.5.2.2 Structural materials
  • 1.5.2.3 Coolant materials
  • 1.5.2.4 Moderating materials
  • 1.5.2.5 Control materials
  • 1.5.2.6 Reflective layer materials
  • 1.5.2.7 Shielding materials
  • 1.5.3 Performance requirement for nuclear reactor advanced fuels and materials
  • 1.5.3.1 Neutron absorption cross-sections
  • 1.5.3.2 Irradiation stability
  • 1.5.3.3 Corrosion resistance
  • 1.5.3.4 Mechanical properties
  • 1.5.3.5 Thermophysical properties
  • 1.5.3.6 Compatibility
  • Bibliography
  • 2 Fundamentals of nuclear materials
  • 2.1 Overview of the fundamentals of materials science
  • 2.1.1 Crystal structure of materials
  • 2.1.2 Phase structure of materials
  • 2.1.2.1 Composition of phases
  • 2.1.2.1.1 Monomer
  • 2.1.2.1.2 Solid solution
  • 2.1.2.1.3 Compounds
  • 2.1.2.2 Phase transitions
  • 2.1.2.3 Phase diagrams
  • 2.1.3 Defects in materials
  • 2.1.3.1 Point defects
  • 2.1.3.2 Line defects
  • 2.1.3.3 Surface defects
  • 2.1.3.3.1 Grain boundaries
  • 2.1.3.3.2 Phase boundary
  • 2.1.3.3.3 Twin boundary
  • 2.1.3.3.4 Stacking fault
  • 2.2 Basic preparation methods for materials
  • 2.2.1 Methods of powder preparation
  • 2.2.1.1 Solid-phase reaction method
  • 2.2.1.2 Sol-gel method
  • 2.2.1.3 Coprecipitation
  • 2.2.2 Metal processes
  • 2.2.2.1 Casting process
  • 2.2.2.2 Powder metallurgy
  • 2.2.2.3 Pressure processing
  • 2.2.3 Ceramic processes
  • 2.2.4 Coating processes
  • 2.2.4.1 Physical vapor deposition
  • 2.2.4.2 Chemical vapor deposition
  • 2.3 Material characterization methods
  • 2.3.1 Morphological observations
  • 2.3.1.1 Scanning electron microscopy
  • 2.3.1.2 Transmission electron microscope
  • 2.3.2 Composition analysis
  • 2.3.3 Structural analysis
  • 2.3.4 Surface chemical state analysis
  • 2.3.4.1 X-ray photoelectron spectroscopy
  • 2.3.4.2 Auger electron spectroscopy.
  • 2.3.5 Spectroscopic analysis techniques
  • 2.4 Fundamentals of material irradiation effects
  • 2.4.1 Irradiation damage
  • 2.4.1.1 Types of irradiation damage
  • 2.4.1.2 Collision and energy transfer process
  • 2.4.1.3 Dislocation peak and thermal peak
  • 2.4.2 Irradiation defects
  • 2.4.2.1 The process of irradiation defect formation
  • 2.4.2.2 Reaction to point defects
  • 2.4.2.3 Factors influencing irradiation defects
  • 2.4.2.3.1 Temperature
  • 2.4.2.3.2 Lattice type
  • 2.4.2.3.3 Chemical composition
  • 2.4.2.3.4 Other types of radiation defects
  • Irradiation-induced segregation
  • Phase transition induced by irradiation
  • Irradiation induced amorphous
  • The production of exogenous atoms
  • 2.4.3 Irradiation effects
  • 2.4.3.1 Irradiation swelling
  • 2.4.3.2 Irradiation creep
  • 2.4.3.3 Irradiation hardening and embrittlement
  • 2.4.4 Examples of irradiation effects
  • 2.4.4.1 "Irradiation growth" of zirconium-plutonium alloy
  • 2.4.4.2 "Shrinkage followed by expansion" under irradiation of graphite materials
  • Bibliography
  • 3 Overview of the nuclear fuel cycle
  • 3.1 Nuclear fuel cycle process
  • 3.1.1 Nuclear fuel cycle system
  • 3.1.1.1 The uranium fuel cycle
  • 3.1.1.2 Uranium-plutonium fuel cycle
  • 3.1.1.3 Thorium-uranium fuel cycle
  • 3.1.2 Nuclear fuel cycle modes
  • 3.1.2.1 One-through cycle
  • 3.1.2.2 Reprocessing fuel cycle
  • 3.2 Uranium resources and uranium metallurgy
  • 3.2.1 Uranium resources classification and distribution
  • 3.2.2 Uranium ore classification
  • 3.2.2.1 Primary ore
  • 3.2.2.2 Secondary ore
  • 3.2.3 Uranium mining
  • 3.2.4 Uranium smelting
  • 3.3 Uranium conversion
  • 3.3.1 UO2 preparation from uranium chemical concentrate
  • 3.3.2 UF4 preparation by hydrofluorination of UO2
  • 3.3.2.1 Wet preparation of UF4
  • 3.3.2.2 Dry preparation of UF4
  • 3.3.3 Preparation of UF6 from UF4.
  • 3.3.3.1 Refined UF4 fluorination method
  • 3.3.3.2 Fluoride volatilization method
  • 3.3.4 Preparation of uranium metal
  • 3.4 Uranium enrichment
  • 3.4.1 Gas diffusion method
  • 3.4.2 Gas centrifugation method
  • 3.4.3 Laser separation method
  • 3.5 Manufacturing of fuel elements (components)
  • 3.5.1 Production reactor fuel assemblies
  • 3.5.2 Light water reactor fuel assemblies
  • 3.5.3 Heavy water reactor fuel assemblies
  • 3.5.4 High-temperature gas-cooled reactor fuel elements
  • 3.5.5 Sodium-cooled fast neutron reactor fuel assembly
  • 3.5.6 Research test reactor fuel elements
  • 3.6 In-reactor use
  • 3.6.1 Neutron cycle
  • 3.6.2 Reactor criticality
  • 3.7 Reprocessing of nuclear fuel
  • 3.7.1 Spent fuel reprocessing process
  • 3.7.1.1 Bismuth phosphate process
  • 3.7.1.2 Redox process
  • 3.7.1.3 The Trigly process
  • 3.7.1.4 Butex process
  • 3.7.1.5 Purex process
  • 3.7.1.6 Thorex process
  • 3.7.1.7 Trialkylphosphine oxide process
  • 3.7.2 Spent fuel reprocessing process flow
  • 3.7.2.1 Spent fuel element first-end processing
  • 3.7.2.2 Uranium-plutonium codecontamination and separation cycle
  • 3.7.2.3 Plutonium purification cycle and tail-end processing
  • 3.7.2.4 Uranium purification cycle and tail-end treatment
  • Bibliography
  • 4 Metal and alloy fuels
  • 4.1 Uranium metal
  • 4.1.1 Basic properties of uranium
  • 4.1.2 Irradiation behavior of uranium
  • 4.2 Uranium alloys
  • 4.2.1 U-Mo alloy
  • 4.2.1.1 Basic properties of U-Mo alloy
  • 4.2.1.2 Preparation of U-Mo alloy
  • 4.2.1.3 Irradiation properties of U-Mo alloy
  • 4.2.2 U-Zr and U-Pu-Zr alloys
  • 4.2.2.1 Basic properties of U-Zr alloy
  • 4.2.2.2 Basic properties of U-Pu-Zr alloy
  • 4.2.2.3 Fabrication of alloy fuels
  • 4.2.2.4 Irradiation behaviors of U-Pu-Zr alloy
  • 4.2.2.4.1 Fuel component migration
  • 4.2.2.4.2 Fission gas release and gas swelling.
  • 4.2.2.4.3 Fuel block re-structuring and deformation
  • 4.2.2.4.4 Fuel-cladding mechanical interactions
  • 4.2.2.4.5 Fuel-cladding chemical interactions
  • 4.3 Uranium intermetallic compounds
  • 4.3.1 Fuel structure
  • 4.3.2 U-Al alloys
  • 4.3.3 U-Si alloy
  • 4.3.4 Irradiation behavior of uranium intermetallic compounds
  • 4.3.4.1 Blistering
  • 4.3.4.2 Amorphization
  • 4.3.4.3 Swelling
  • 4.3.4.4 Fuel-substrate interactions
  • 4.4 U-Zr-H fuel system
  • 4.4.1 Application of U-Zr-H fuel
  • 4.4.1.1 Systems for Nuclear Auxiliary Power Project reactor
  • 4.4.1.2 Training, research, isotopes, general, atomics reactor
  • 4.4.1.3 Transmutation reactors
  • 4.4.2 Basic properties of U-Zr-H fuels
  • 4.4.3 Fabrication of U-Zr-H fuels
  • 4.4.4 Irradiation behavior of U-Zr-H fuels
  • Bibliography
  • 5 Oxide fuels
  • 5.1 Properties of uranium dioxide
  • 5.1.1 Thermal properties
  • 5.1.1.1 Thermal conductivity
  • 5.1.1.2 Heat capacity
  • 5.1.1.3 Thermal expansion coefficient
  • 5.1.2 Mechanical properties
  • 5.1.3 Chemical properties
  • 5.2 Preparation of uranium dioxide pellets
  • 5.2.1 Preparation of uranium dioxide powder
  • 5.2.1.1 Ammonium diuranate method
  • 5.2.1.2 Ammonium uranyl carbonate method
  • 5.2.1.3 Integrated dry route method
  • 5.2.1.4 Flame method
  • 5.2.2 Forming
  • 5.2.2.1 Mixture
  • 5.2.2.2 Pelleting
  • 5.2.2.3 Compression
  • 5.2.3 Sintering
  • 5.2.3.1 Conventional sintering
  • 5.2.3.2 Field assisted sintering
  • 5.2.3.2.1 Microwave sintering
  • 5.2.3.2.2 High frequency induction heating sintering
  • 5.2.3.2.3 Spark plasma sintering
  • 5.2.3.2.4 Flash sintering
  • 5.2.3.3 Micro-oxidation sintering
  • 5.2.4 Grinding
  • 5.2.5 Perfect fuel pellet
  • 5.2.6 Preparation of burnable poison uranium dioxide pellets
  • 5.3 Manufacture of uranium dioxide fuel rod
  • 5.3.1 Basic structure of fuel rod
  • 5.3.2 Cladding material.