| Description |
1 online resource |
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text txt rdacontent |
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computer c rdamedia |
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online resource cr rdacarrier |
| Series |
Woodhead Publishing series in energy ; number 106 |
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Woodhead Publishing in energy ; no. 106.
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| Bibliography |
Includes bibliographical references and index. |
| Note |
Online resource; title from PDF title page (EBSCO, viewed September 1, 2016). |
| Summary |
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. |
| Contents |
Front Cover; Structural Materials for Generation IV Nuclear Reactors; Related titles; Structural Materials for Generation IV Nuclear Reactors ; Copyright; Contents; List of contributors; Woodhead Publishing Series in Energy; Introduction; 1 -- Introduction to Generation IV nuclear reactors; 1.1 Introduction: the need for new nuclear systems; 1.2 Generation IV requirements and technical challenges; 1.2.1 Development of sustainable nuclear energy; 1.2.2 Maintaining or increasing competitiveness; 1.2.3 Improving and enhancing safety and reliability |
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1.2.4 Ensuring proliferation resistance and physical protection1.3 Generation IV systems fulfilling these requirements; 1.3.1 Gas-cooled systems; 1.3.2 Liquid metal-cooled systems; 1.3.3 Molten salt; 1.3.4 Water-cooled systems; 1.4 Conclusion; References; 2 -- Corrosion phenomena induced by liquid metals in Generation IV reactors; 2.1 Introduction to the liquid metals selected for Generation IV reactors; 2.2 Thermal, physical, and chemical properties of the liquid metals; 2.2.1 Solubility limits in liquid metal; 2.2.1.1 Solubility of metallic and nonmetallic elements in liquid Na |
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2.2.1.2 Solubility of metallic and nonmetallic elements in liquid Pb and Pb-Bi2.3 The impact of structural material corrosion on reactor operation; 2.4 Parameters affecting corrosion in the liquid metal and experimental procedures; 2.4.1 Dissolution process; 2.4.2 Oxidation process; 2.4.3 Influence of temperature; 2.4.4 Influence of flow velocity; 2.4.5 Influence of carbon; 2.5 Corrosion under reactor conditions: mass transfer, experimental data, and modeling; 2.6 Impact of corrosion on mechanical strength of the structural material |
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2.6.1 Impact of Na on mechanical properties of reference structural materials2.6.1.1 Effect of carbon in Na; 2.6.1.2 Effect of oxygen in Na; 2.6.1.3 Na and neutron irradiation synergetic effects; 2.6.1.4 Impact on component design; 2.6.2 Impact of Pb and Pb-Bi on mechanical properties of reference structural materials; 2.6.2.1 Tensile properties in Pb and Pb-Bi; 2.6.2.2 Creep and creep-to-rupture properties; 2.6.2.3 Low cycle fatigue properties; 2.6.2.4 Pb/Pb-Bi and irradiation fields; 2.6.2.5 Impact on component design; 2.7 Corrosion mitigation; 2.7.1 Corrosion mitigation for SFR |
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2.7.2 Corrosion mitigation for LFR2.8 Conclusions; References; 3 -- Corrosion phenomena induced by gases in Generation IV nuclear reactors; 3.1 Corrosion of IHX alloys in impure helium of a VHTR system; 3.1.1 VHTR atmosphere; 3.1.2 Chemical reactivity between metallic surfaces and VHTR helium at high temperature; 3.1.3 Rapid carburization/decarburization of alloys in improper helium; 3.1.4 Long-term evolution of alloys in chemically controlled oxidizing helium; 3.2 Corrosion phenomena in supercritical CO2; 3.2.1 Mild steels; 3.2.2 9-12Cr ferritic-martensitic steels |
| Subject |
Nuclear reactors -- Materials.
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Nuclear energy.
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Building materials.
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Réacteurs nucléaires -- Matériaux.
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Énergie nucléaire.
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Construction -- Matériaux.
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nuclear power.
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building materials.
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TECHNOLOGY & ENGINEERING -- Mechanical.
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Building materials
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Nuclear energy
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Nuclear reactors -- Materials
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| Added Author |
Yvon, Pascal, editor.
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| ISBN |
9780081009123 (electronic bk.) |
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0081009127 (electronic bk.) |
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9780081009062 |
| Standard No. |
AU@ 000058968542 |
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CHNEW 001013766 |
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DEBSZ 482473193 |
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GBVCP 879419822 |
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UKMGB 018086751 |
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