Irradiation Creep in Materials

Fabien Onimus, Thomas Jourdan, Cheng Xu, Anne A. Campbell, Malcolm Griffiths

Research output: Chapter in Book/Report/Conference proceedingChapterpeer-review

26 Scopus citations

Abstract

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 article, 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-martensitic steels and graphite, is described.

Original languageEnglish
Title of host publicationComprehensive Nuclear Materials
Subtitle of host publicationSecond Edition
PublisherElsevier
Pages310-366
Number of pages57
ISBN (Electronic)9780081028650
ISBN (Print)9780081028667
DOIs
StatePublished - Jul 22 2020

Keywords

  • Austenitic stainless steel
  • Climb
  • Creep
  • Diffusion
  • Dislocation
  • Ferritic steel
  • Ferritic-martensitic steel
  • Glide
  • Graphite
  • Irradiation
  • Loop
  • Nickel based alloys
  • Point defects
  • Zirconium alloys

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