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Structural Materials for Generation IV Nuclear Reactors
1st Edition - August 27, 2016
Editor: Pascal Yvon
Hardback ISBN:9780081009062
9 7 8 - 0 - 0 8 - 1 0 0 9 0 6 - 2
eBook ISBN:9780081009123
9 7 8 - 0 - 0 8 - 1 0 0 9 1 2 - 3
Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy… Read more
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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.
Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials
Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates
Written by an expert in that particular area
Professional scientists and engineers involved in the development of generation IV nuclear reactors as well as postgraduate researchers in academia working on generation IV nuclear reactors.
Related titles
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
1.3. Generation IV systems fulfilling these requirements
1.4. Conclusion
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
2.3. The impact of structural material corrosion on reactor operation
2.4. Parameters affecting corrosion in the liquid metal and experimental procedures
2.5. Corrosion under reactor conditions: mass transfer, experimental data, and modeling
2.6. Impact of corrosion on mechanical strength of the structural material
2.7. Corrosion mitigation
2.8. Conclusions
3. Corrosion phenomena induced by gases in Generation IV nuclear reactors
3.1. Corrosion of IHX alloys in impure helium of a VHTR system
3.2. Corrosion phenomena in supercritical CO2
3.3. Concluding remarks
4. Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors
4.1. Introduction
4.2. What is supercritical water?
4.3. Test methodologies
4.4. General corrosion in SCW
4.5. Environmentally assisted cracking
4.6. Summary
5. Corrosion phenomena induced by molten salts in Generation IV nuclear reactors
5.1. Introduction: molten salts in Generation IV nuclear reactors
5.2. Requirements and molten salt mixtures available
5.3. Corrosion processes in molten salts
5.4. Salt chemistry control
5.5. Materials and corrosion data for different reactor systems and components
5.6. Conclusion
6. Mechanical behavior of structural materials for Generation IV reactors
6.1. Introduction
6.2. Mechanical properties of F-M steels
6.3. Analysis of the macroscopic behavior of martensitic steels for low loads
6.4. Microstructural changes during the strain of martensitic steels at low loads
6.5. Elements of a martensitic steel softening model
6.6. Damage and fracture in fatigue and creep
6.7. Recent progresses concerning long-term creep and fatigue behavior of austenitic stainless steels
6.8. Conclusions and recommended further work
7. Irradiation effects in Generation IV nuclear reactor materials
7.1. Introduction
7.2. Radiation damage process
7.3. Advances in characterization of defects in irradiated materials
7.4. Mesoscale modeling of radiation damage
7.5. Summary
8. Irradiation-resistant austenitic steels as core materials for Generation IV nuclear reactors
8.1. Introduction
8.2. Austenitic steels and Generation IV systems
8.3. Out-of-pile characteristics of reference austenitic steels
8.4. In-pile and postirradiation mechanical properties of reference austenitic steels
8.5. Swelling and irradiation creep properties of reference austenitic steels
8.6. Development of advanced austenitic materials designed to increase the in-pile duration of core structures of Generation IV systems
8.7. Conclusion
Glossary
9. Irradiation-resistant ferritic and martensitic steels as core materials for Generation IV nuclear reactors
9.1. Introduction
9.2. Use of ferritic-martensitic steels in fast reactors and future Generation IV reactors
9.3. Irradiation effects in ferritic-martensitic steels
9.4. Advanced ferritic-martensitic steels with improved thermal creep resistance
9.5. Summary
Abbreviations
10. Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors
10.1. Introduction
10.2. Nanosized oxide particle control
10.3. Development of oxide dispersion-strengthened steels in Japan
10.4. Development of oxide dispersion-strengthened steels in France
10.5. Development of other oxide dispersion-strengthened steels
10.6. Joining
10.7. Environmental compatibility
10.8. Irradiation
10.9. Conclusion
11. Refractory metals as core materials for Generation IV nuclear reactors
11.1. Refractory metals for nuclear application
11.2. V and its alloys
11.3. Nb, Ta, Mo, W, and their alloys
11.4. Summary
12. SiCf/SiC composites as core materials for Generation IV nuclear reactors
12.1. Introduction
12.2. Potential use in Generation IV systems
12.3. Fabrication and role of each constituent of the SiCf/SiC composite and matrix filling technologies
12.4. Behavior of the SiCf/SiC composite in operating conditions
12.5. Codes and standards
12.6. Summary
13. Carbon/carbon materials for Generation IV nuclear reactors
13.1. Introduction
13.2. Potential use in Generation IV systems
13.3. Fabrication and role of each constituent of C/C composites and matrix filling technologies
13.4. Behavior of C/C in operating conditions
13.5. Standards and codes
13.6. Conclusions
14. Graphite as a core material for Generation IV nuclear reactors
14.1. Introduction
14.2. Nuclear graphite grades, their manufacture, microstructure, and properties
14.3. Nuclear graphite irradiation-induced dimensional and property changes
14.4. Component structural integrity
14.5. Thermal oxidation in fault conditions
14.6. Dealing with irradiated graphite waste
14.7. Advances in the treatment of graphite and carbowastes
14.8. Molten salt reactors—graphite
14.9. Discussion and conclusions
15. Absorber materials for Generation IV reactors
15.1. Introduction: neutron absorbers for Generation IV reactors
15.2. Scaling the neutron absorbers
15.3. Behavior under irradiation of neutron absorber materials
15.4. Conclusion: for a better definition of the needs
Abbreviations
16. Advanced irradiation-resistant materials for Generation IV nuclear reactors
16.1. Introduction
16.2. Identification of potential advanced irradiation-resistant materials
16.3. Basic properties
16.4. Fabrication and joining
16.5. Experimental feedback and possible applications
16.6. Future trends and conclusions
17. Conventional austenitic steels as out-of-core materials for Generation IV nuclear reactors
17.1. Introduction
17.2. General overview of austenitic steels in Generation IV frame
17.3. Choice of austenitic steel grades for future French SFR out-of-core components
17.4. Basic physical, thermal, and mechanical properties
17.5. Fabrication and joining
17.6. Long-term mechanical behavior in operating conditions
17.7. Corrosion and oxidation behavior
17.8. Low-dose irradiation
17.9. Codes and standards
17.10. New alloy development
17.11. Conclusions
Glossary
18. Conventional ferritic and martensitic steels as out-of-core materials for Generation IV nuclear reactors
18.1. Introduction—attractive characteristics for Generation IV nuclear plants
18.2. Pedigree of materials
18.3. Application and challenges
18.4. Evaluation technologies
18.5. Fabrication technologies
18.6. Code qualification
18.7. Summary
Index
No. of pages: 684
Language: English
Published: August 27, 2016
Imprint: Woodhead Publishing
Hardback ISBN: 9780081009062
eBook ISBN: 9780081009123
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Pascal Yvon
Pascal Yvon graduated in 1984 from Ecole Centrale Paris (France). He subsequently obtained a Master in Materials Science in 1986 and a PhD in Applied Physics from the California Institute of Technology (USA) for his work on pressure induced crystal to amorphous transformation in the Al-Ge system. After working as a research assistant at the Center for Material Science at the Los Alamos National Laboratory (USA), he worked at the Institute for Advanced Materials in Petten (The Netherlands), before joining CEA in 1996, where he was in charge of studies on the behavior under irradiation of zirconium alloys. Then he held several management positions in the Department of Materials for Nuclear applications, before becoming in 2006 program manager for high temperature reactors, hydrogen production and non-electric applications. Since 2009, Pascal YVON has been the head of the Department of Materials for Nuclear applications of the Nuclear Energy Division of CEA.
Affiliations and expertise
CEA (Commissariat à l’énergie atomique et aux énergies alternatives), France