期刊论文详细信息
JOURNAL OF NUCLEAR MATERIALS 卷:500
Effect of post-irradiation annealing on the irradiated microstructure of neutron-irradiated 304L stainless steel
Article
Jiao, Z.1  Hesterberg, J.1  Was, G. S.1 
[1] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
关键词: Microstructure;    Radiation-induced segregation;    Post-irradiation annealing;   
DOI  :  10.1016/j.jnucmat.2017.12.030
来源: Elsevier
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【 摘 要 】

Post-irradiation annealing was performed on a 304L SS that was irradiated to 5.9 dpa in the Barseback 1 BWR reactor. Evolution of dislocation loops, radiation-induced solute clusters and radiation-induced segregation at the grain boundary was investigated following thermal annealing at 500 degrees C and 550 degrees C up to 20 h. Dislocation loops, Ni-Si and Al-Cu clusters, and enrichment of Ni, Si and depletion of Cr at the grain boundary were observed in the as-irradiated condition. Dislocation loop size did not change significantly after annealing at 550 degrees C for 5 h but the loop number density decreased considerably and loops mostly disappeared after annealing at 550 degrees C for 20 h. The average size of Ni-Si and Al-Cu clusters increased while the number density decreased with annealing. The increase in cluster size was due to diffusion of solutes rather than cluster coarsening. Significant volume fractions of Ni-Si and Al-Cu clusters still remained after annealing at 550 degrees C for 20 h. Substantial recovery of Cr and Ni at the grain boundary was observed after annealing at 550 degrees C for 5 h but neither Cr nor Ni was fully recovered after 20 h. Annihilation of dislocation loops, driven by the thermal vacancy concentration gradient caused by the strain field and stacking fault associated with the loops appeared to be faster than annihilation of solute clusters and recovery of Ni and Si at the grain boundary, both of which are driven by the solute concentration gradients. (c) 2018 Elsevier B.V. All rights reserved.

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