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Irradiation creep in materials

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  • معلومة اضافية
    • Contributors:
      Service des Recherches Métallurgiques Appliquées (SRMA); Département des Matériaux pour le Nucléaire (DMN); CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)); Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)); Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay; Service de recherches de métallurgie physique (SRMP); TerraPower; Oak Ridge National Laboratory Oak Ridge (ORNL); UT-Battelle, LLC; Queen's University Kingston, Canada; R. Konings; R. Stoller
    • بيانات النشر:
      HAL CCSD
      Elsevier
    • الموضوع:
      2021
    • نبذة مختصرة :
      SEcond edition ; International audience ; A knowledge of the dimensional stability of reactor structural components, under irradiation conditions, is of major importance in the design of thermal, fast, and fusion reactors. When subjected to simultaneous mechanical loading and irradiation, structural materials exhibit a visco-plastic deformation phenomenon, referred to as irradiation creep, which can be more rapid than the deformation occurring out of irradiation. In this chapter, the phenomenology of this peculiar behavior is described after a short history of its discovery. Then, the theoretical mechanisms proposed in the literature during these past 60 years are presented, with a special focus on mechanisms based on stress induced preferred absorption of point defects by dislocation loops, dislocations and grain boundaries and on mechanisms based on climb-enhanced glide of dislocations. These mechanisms are discussed in the light of experimental evidences. Finally, irradiation creep in various materials, such as zirconium alloys, austenitic stainless steels, nickel-based alloys, ferritic steels, ferritic-martensitic and also graphite, is described.
    • ISBN:
      978-0-12-803581-8
      0-12-803581-1
      978-0-08-102866-7
      0-08-102866-0
    • Relation:
      hal-04065942; https://hal.science/hal-04065942; https://hal.science/hal-04065942v2/document; https://hal.science/hal-04065942v2/file/OnimusComprNuclMater_IrrCreep_HAL.pdf
    • الرقم المعرف:
      10.1016/B978-0-12-803581-8.11645-5
    • Rights:
      info:eu-repo/semantics/OpenAccess
    • الرقم المعرف:
      edsbas.F3FB9F38