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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

1. Introduction - p. xix 2. 1. Introduction to Generation IV nuclear reactors - p. 1 3. 2. Corrosion phenomena induced by liquid metals in Generation IV reactors - p. 23 4. 3. Corrosion phenomena induced by gases in Generation IV nuclear reactors - p. 75 5. 4. Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors - p. 105 6. 5. Corrosion phenomena induced by molten salts in Generation IV nuclear reactors - p. 153 7. 6. Mechanical behavior of structural materials for Generation IV reactors - p. 191 8. 6.1. Introduction - p. 191 9. 6.2. Mechanical properties of F-M steels - p. 194 10. 6.3. Analysis of the macroscopic behavior of martensitic steels for low loads - p. 198 11. 6.4. Microstructural changes during the strain of martensitic steels at low loads - p. 205 12. 6.5. Elements of a martensitic steel softening model - p. 209 13. 6.6. Damage and fracture in fatigue and creep - p. 216 14. 6.7. Recent progresses concerning long-term creep and fatigue behavior of austenitic stainless steels - p. 227 15. 6.8. Conclusions and recommended further work - p. 245 16. 7. Irradiation effects in Generation IV nuclear reactor materials - p. 253 17. 8. Irradiation-resistant austenitic steels as core materials for Generation IV nuclear reactors - p. 285 18. 9. Irradiation-resistant ferritic and martensitic steels as core materials for Generation IV nuclear reactors - p. 329 19. 10. Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors - p. 357 20. 11. Refractory metals as core materials for Generation IV nuclear reactors - p. 415 21. 12. SiCf/SiC composites as core materials for Generation IV nuclear reactors - p. 441 22. 13. Carbon/carbon materials for Generation IV nuclear reactors - p. 471 23. 14. Graphite as a core material for Generation IV nuclear reactors - p. 495 24. 15. Absorber materials for Generation IV reactors - p. 533 25. 16. Advanced irradiation-resistant materials for Generation IV nuclear reactors - p. 569 26. 17. Conventional austenitic steels as out-of-core materials for Generation IV nuclear reactors - p. 595 27. 18. Conventional ferritic and martensitic steels as out-of-core materials for Generation IV nuclear reactors - p. 635 28. Index - p. 651

Descripcion
Descripción

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

1. Introduction - p. xix 2. 1. Introduction to Generation IV nuclear reactors - p. 1 3. 2. Corrosion phenomena induced by liquid metals in Generation IV reactors - p. 23 4. 3. Corrosion phenomena induced by gases in Generation IV nuclear reactors - p. 75 5. 4. Corrosion phenomena induced by supercritical water in Generation IV nuclear reactors - p. 105 6. 5. Corrosion phenomena induced by molten salts in Generation IV nuclear reactors - p. 153 7. 6. Mechanical behavior of structural materials for Generation IV reactors - p. 191 8. 6.1. Introduction - p. 191 9. 6.2. Mechanical properties of F-M steels - p. 194 10. 6.3. Analysis of the macroscopic behavior of martensitic steels for low loads - p. 198 11. 6.4. Microstructural changes during the strain of martensitic steels at low loads - p. 205 12. 6.5. Elements of a martensitic steel softening model - p. 209 13. 6.6. Damage and fracture in fatigue and creep - p. 216 14. 6.7. Recent progresses concerning long-term creep and fatigue behavior of austenitic stainless steels - p. 227 15. 6.8. Conclusions and recommended further work - p. 245 16. 7. Irradiation effects in Generation IV nuclear reactor materials - p. 253 17. 8. Irradiation-resistant austenitic steels as core materials for Generation IV nuclear reactors - p. 285 18. 9. Irradiation-resistant ferritic and martensitic steels as core materials for Generation IV nuclear reactors - p. 329 19. 10. Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors - p. 357 20. 11. Refractory metals as core materials for Generation IV nuclear reactors - p. 415 21. 12. SiCf/SiC composites as core materials for Generation IV nuclear reactors - p. 441 22. 13. Carbon/carbon materials for Generation IV nuclear reactors - p. 471 23. 14. Graphite as a core material for Generation IV nuclear reactors - p. 495 24. 15. Absorber materials for Generation IV reactors - p. 533 25. 16. Advanced irradiation-resistant materials for Generation IV nuclear reactors - p. 569 26. 17. Conventional austenitic steels as out-of-core materials for Generation IV nuclear reactors - p. 595 27. 18. Conventional ferritic and martensitic steels as out-of-core materials for Generation IV nuclear reactors - p. 635 28. Index - p. 651

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