Effect of friction stir welding and post-weld heat treatment on a nanostructured ferritic alloy

Mazumder, Baishakhi; Yu, Xinghua; Edmondson, Philip D.; Parish, Chad M.; Miller, Michael K; Meyer, H. M.; Feng, Zhili

doi:10.1016/j.jnucmat.2015.11.061

Title: Effect of friction stir welding and post-weld heat treatment on a nanostructured ferritic alloy

Journal Article · Tue Dec 08 00:00:00 EST 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2015.11.061· OSTI ID:1286916

Mazumder, Baishakhi ^[1]; Yu, Xinghua ^[1]; Edmondson, Philip D. ^[1]; Parish, Chad M. ^[1]; Miller, Michael K ^[1]; Meyer, H. M. ^[1]; Feng, Zhili ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Nanostructured ferritic alloys (NFAs) are new generation materials for use in high temperature energy systems, such as nuclear fission or fusion reactors. However, joining these materials is a concern, as their unique microstructure is destroyed by traditional liquid-state welding methods. The microstructural evolution of a friction stir welded 14YWT NFA was investigated by atom probe tomography, before and after a post-weld heat treatment (PWHT) at 1123K. The particle size, number density, elemental composition, and morphology of the titanium-yttrium-oxygenenriched nanoclusters (NCs) in the stir and thermally-affected zones were studied and compared with the base metal. No statistical difference in the size of the NCs was observed in any of these conditions. After the PWHT, increases in the number density and the oxygen enrichment in the NCs were observed. Therefore, these new results provide additional supporting evidence that friction stir welding appears to be a viable joining technique for NFAs, as the microstructural parameters of the NCs are not strongly affected, in contrast to traditional welding techniques.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Center for Nanophase Materials Sciences (CNMS)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725; ERKCM52

OSTI ID:: 1286916

Alternate ID(s):: OSTI ID: 1396699

Journal Information:: Journal of Nuclear Materials, Vol. 469; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 14 works

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