Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

JOURNAL OF NUCLEAR MATERIALS

卷:489

Article

Field, Kevin G.¹  Briggs, Samuel A.²  Sridharan, Kumar²  Howard, Richard H.¹  Yamamoto, Yukinori¹ 

[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[2] Univ Wisconsin, Madison, WI 53706 USA

关键词: FeCrAl;    Accident tolerant;    Mechanical properties;   

DOI  :  10.1016/j.jnucmat.2017.03.038

来源: Elsevier

【 摘 要 】

The development and understanding of the mechanical properties of neutron-irradiated FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature for nuclear reactor applications. This study focuses on the mechanical properties of model FeCrAl alloys and of a commercial FeCrAl alloy neutron-irradiated to up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382 degrees C. Tensile tests were completed at room temperature and at 320 degrees C, and a subset of fractured tensile specimens was examined by scanning electron microscopy. Results showed typical radiation hardening and embrittlement indicative of high chromium ferritic alloys with strong chromium composition dependencies at lower doses. At and above 7.0 dpa, the mechanical properties saturated for both the commercial and model FeCrAl alloys, although brittle cleavage fracture was observed at the highest dose in the model FeCrAl alloy with the highest chromium content (18 wt %). The results suggest the composition and microstructure of FeCrAl alloys plays a critical role in the mechanical response of FeCrAl alloys irradiated near temperatures relevant to light water reactors. (C) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

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