Nuclear corrosion : research, progress and challenges /

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Detalles Bibliográficos
Clasificación:Libro Electrónico
Otros Autores: Ritter, Stefan, 1974- (Editor )
Formato: Electrónico eBook
Idioma:Inglés
Publicado: Duxford : Woodhead Publishing, 2020
Colección:European Federation of Corrosion (EFC) Series
Temas:
Nuclear power plants > Corrosion.
Corrosion and anti-corrosives.
Centrales nucl�eaires > Corrosion.
Corrosion and anti-corrosives
Nuclear power plants > Corrosion
Acceso en línea:Texto completo
Tabla de Contenidos:
  • Front Cover
  • Nuclear Corrosion: Research, Progress and Challenges
  • Copyright Page
  • Contents
  • European Federation of Corrosion publications: Series introduction
  • Volumes in the EFC series
  • List of Contributors
  • European Federation of Corrosion Series No. 69-Nuclear corrosion: research, progress and challenges
  • Some important abbreviations
  • Preface
  • 1 Fifty years of nuclear corrosion in Europe: Evolutions and contributions of the working party on nuclear corrosion
  • 1.1 The early days of nuclear energy
  • 1.2 Foundation and chairmanship of the Working Party 4 on nuclear corrosion
  • 1.3 Main activities of the Working Party 4 on nuclear corrosion
  • 1.3.1 Working Party 4 support to EUROCORR
  • 1.3.2 Working Party 4 support to the European corrosion community
  • 1.3.3 Other Working Party 4 specific events
  • 1.3.4 Knowledge transfer and dissemination efforts of the Working Party 4
  • 1.3.5 Working Party 4 awards
  • 1.4 Summary of past, current, and future challenges
  • References
  • Books in the EFC series ("green books") published under the guidance of the WP 4
  • Other publications and special issues published under the guidance of the WP4
  • 2 Environmentally-assisted cracking of stainless steels in light water reactors
  • 2.1 Introduction
  • 2.2 Components made of stainless steels in boiling water reactors and pressurized water reactors
  • 2.3 Welding of stainless steels
  • 2.4 Stress corrosion cracking
  • 2.4.1 Intergranular stress corrosion cracking in boiling water reactor environments
  • 2.4.1.1 Degree of sensitization
  • 2.4.1.2 Deformation
  • 2.4.1.3 Environment
  • 2.4.1.4 Stress
  • 2.4.2 Mechanistic understanding
  • 2.4.3 Components at risk and plant operation experience in boiling water reactor environment
  • 2.4.3.1 Early intergranular stress corrosion cracking cases in sensitized Type 304 stainless steel
  • 2.4.3.2 Intergranular stress corrosion cracking cases in Ti-stabilized stainless steel
  • 2.4.3.3 Intergranular stress corrosion cracking cases in nonsensitized stainless steel
  • 2.4.3.4 Intergranular stress corrosion cracking in pressurized water reactor environment
  • 2.5 Future research needs
  • Acknowledgments
  • References
  • 3 Mechanisms behind irradiation-assisted stress corrosion cracking
  • 3.1 Introduction
  • 3.2 Radiation effects potentially impacting irradiation-assisted stress corrosion cracking
  • 3.2.1 Radiation-induced segregation at grain boundaries
  • 3.2.2 Dislocation loop microstructure
  • 3.2.3 Radiation-induced hardening and localized deformation
  • 3.2.4 Radiation-induced precipitation
  • 3.2.5 Radiation creep, swelling, and transmutation to form H and He
  • 3.3 Assessment of mechanisms
  • 3.3.1 Radiation-induced segregation
  • 3.3.2 Radiation hardening and localized deformation
  • 3.3.3 Phase stability under irradiation

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