Structural Materials for Generation IV Nuclear Reactors

Forfatter: info mangler
Bog
  • Format
  • Bog, hardback
  • Engelsk

Beskrivelse

Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas.Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors.

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Detaljer
  • SprogEngelsk
  • Sidetal684
  • Udgivelsesdato23-09-2016
  • ISBN139780081009062
  • Forlag Woodhead Publishing Ltd
  • FormatHardback
Størrelse og vægt
  • Vægt1230 g
  • coffee cup img
    10 cm
    book img
    15,1 cm
    22,9 cm

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    Aging Fatigue Microstructure Oxidation Reliability Stability Graphite Properties Porosity Welding Safety Steel Nuclear reactors Modeling Mass transfer Carbon fibers Experiments Corrosion Radiation effects Brittleness Creep Waste Tellurium Structures Fast neutrons Fabrication Molten salt reactors Codes Ferrite Fast reactors Pitch Martensite Phase transformations Codes and standards Irradiation Creep fatigue Expansion Characterization techniques Mechanism Applications CVI Swelling Generation IV Microstructure evolution High Temperature C/C Composites Competetiveness Nuclear reactor Redox Potential Wrapper Phase transformation Resin Decarburization High-Temperature Strength Embrittlement 1.4970300-Series steels 15-15Ti Advanced austenitic steels AISI 304AISI 316Alloy 800Austenitic stainless steels AUSTENITIC STEELS Austenitic Stainless Steels Cooling System Core materials Control Rods Effect of operating conditions carburization Environmentally assisted cracking D9dpa rate effect fabrication technologies Environmental compatibility Fabrication route Compact Heat Exchangers Corrosion mitigation Ferritic Generation IV systems Gilsocarbon generation IV nuclear reactors Generation IV reactors Generation IV reactor systems High dose Irradiation Creep Impurity control Effect of chemical composition Irradiation-induced defects Liquid metal corrosion Effect of cold work Martensitic Liquid metal embrittlement Fabrication and joining technology Low-dose irradiation Generation IV nuclear systems Generation IV systems fast reactors Fuel pin Fuel salts Neutron properties Nickel-based alloy Neutron absorbers α-β /SiC composite Property and performance physical properties Out-of-core components Oxide dispersion-strengthened (ODS)Recrystallization PNC 316Postirradiation properties Refractory Metals Irradiation-resistant Supercritical water Long-term predictions Thermal and radiation creep Martenistic Solute segregation Mesoscale modeling Tempered martensite-ferritic steels Molten salt fluorides Radiation embrittlement Out-of-core materials Swelling gradient Solution annealing treatment Void lattice sicf Thermal creep resistance Structural core components

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