Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

JOURNAL OF NUCLEAR MATERIALS

卷:467

Article

Dong, Y.¹  Sencer, B. H.²  Garner, F. A.³  Marquis, E. A.¹ 

[1] Univ Michigan, Dept Mat Sci & Engn, Ann Arbor, MI 48109 USA

[2] Idaho Natl Lab, Idaho Falls, ID 83402 USA

[3] Radiat Effects Consulting, Richland, WA 99354 USA

关键词: 304 stainless steel;    Neutron irradiation;    Void swelling;    Precipitation;    Segregation;    Atom probe tomography;   

DOI  :  10.1016/j.jnucmat.2015.10.041

来源: Elsevier

【 摘 要 】

AISI 304 stainless steel was irradiated at 416 degrees C and 450 degrees C at a 4.4 x 10(-9) and 3.05 x 10(-7) dpa/s to similar to 0.4 and similar to 28 dpa, respectively, in the reflector of the EBR-II fast reactor. Both unirradiated and irradiated conditions were examined using standard and scanning transmission electron microscopy, energy dispersive spectroscopy, and atom probe tomography on very small specimens produced by focused ion beam milling. These results are compared with previous electron microscopy examination of 3 mm disks from essentially the same material. By comparing a very low dose specimen with a much higher dose specimen, both derived from a single reactor assembly, it has been demonstrated that the coupled microstructural and microchemical evolution of dislocation loops and other sinks begins very early, with elemental segregation producing at these sinks what appears to be measurable precursors to fully formed precipitates found at higher doses. The nature of these sinks and their possible precursors are examined in detail. (C) 2015 Elsevier B.V. All rights reserved.

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