期刊
JOURNAL OF NUCLEAR MATERIALS
卷 558, 期 -, 页码 -出版社
ELSEVIER
DOI: 10.1016/j.jnucmat.2021.153365
关键词
RAFM steel; Neutron irradiation; Post-irradiation annealing; In-situ TEM; Dislocation loop
资金
- Euratom research and training programme [633053]
The study revealed that post-irradiation annealing at 600 degrees Celsius can effectively reduce the dislocation loop density and increase the average size of loops in 9%Cr reduced-activation ferritic-martensitic steel. The annealing kinetics of loops is significantly affected by the spontaneous evolution of loops neighboring microstructure, as well as the type of loops, segregation of alloying elements, and the presence of free surface.
Post-irradiation annealing (PIA) is beneficial in recovering degraded mechanical properties of irradiated materials due to the evolution of irradiation-induced defects. To understand the underlying responsible mechanisms, isothermal PIA experiments were carried out in this work on a neutron-irradiated 9%Cr reduced-activation ferritic-martensitic steel (EUROFER97) using in-situ transmission electron microscopy. In general, PIA at 600 degrees C led to an appreciable reduction of the dislocation loop density and increment in the loops mean size. This is found mainly associated with the vacancy-mediated loops shrinkage phenomenon. The driving force for this process is loop's curvature force. Nevertheless, the spontaneous evolution of the loops neighboring microstructure substantially alters their annealing kinetics. Therefore, in this study, loops' annealing kinetics in EUROFER97 is discussed in terms of various scenarios originating in terms of the presence or absence of the local external sources and sinks. In addition, influence of loops type, alloying elements segregation and free surface are also discussed. (c) 2021 Elsevier B.V. All rights reserved.
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