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 language | English |
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Title of host publication | Comprehensive Nuclear Materials |
Subtitle of host publication | Second Edition |
Publisher | Elsevier |
Pages | 310-366 |
Number of pages | 57 |
ISBN (Electronic) | 9780081028650 |
ISBN (Print) | 9780081028667 |
DOIs | |
State | Published - 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