Effect of friction stir welding and self-ion irradiation on dispersoid evolution in oxide dispersion strengthened steel MA956 up to 25 dpa

Getto, E.; Baker, B.; Tobie, B.; Briggs, S.; Hattar, K.; Knipling, K.

doi:10.1016/j.jnucmat.2018.12.040

Title: Effect of friction stir welding and self-ion irradiation on dispersoid evolution in oxide dispersion strengthened steel MA956 up to 25 dpa

Journal Article · Mon Dec 24 00:00:00 EST 2018 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2018.12.040· OSTI ID:1650170

Getto, E. ^[1]; Baker, B. ^[1]; Tobie, B. ^[1]; Briggs, S. ^[2]; Hattar, K. ^[3]; Knipling, K. ^[4]

US Naval Academy, Annapolis, MD (United States). Dept. of Mechanical Engineering
Oregon State Univ., Corvallis, OR (United States). School of Nuclear Science and Engineering; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Naval Research Lab. (NRL), Washington, DC (United States). Materials Science and Technology Division

Here, the effect of ion irradiation on the microstructure of oxide dispersion strengthened (ODS) MA956 steel, before and after friction stir welding (FSW), was studied. Both the base material (BM) and welded stir zone (SZ) were irradiated with 5 MeV Fe⁺⁺ ions at 450 °C up to 25 displacements per atom (dpa). Characterization was performed using scanning transmission electron microscopy (STEM) and atom probe tomography (APT), with particular emphasis on the Y—Al—O dispersoid characteristics and dislocation microstructures. After irradiation, the dispersoids in the BM increased in diameter and decreased in number density, which was explained by an Ostwald ripening mechanism. FSW caused significant coarsening and agglomeration of the dispersoids. After irradiation, both the diameter and number density of the SZ dispersoids increased, which was explained by an irradiation-enhanced diffusion mechanism. Dislocation loop and network behavior was also characterized and large dislocation loops of ≈20 nm diameter formed by 1 dpa in both the BM and SZ samples, whereas the network density remained nearly constant with irradiation.

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Research Organization:: Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Basic Energy Sciences (BES); US Naval Academy; USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: AC04-94AL85000; NSUF-RTF-17-906; NA-0003525; AC07-051D14517

OSTI ID:: 1650170

Alternate ID(s):: OSTI ID: 1635970

Report Number(s):: SAND-2020-8426J; 689936; TRN: US2203118

Journal Information:: Journal of Nuclear Materials, Vol. 515; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 9 works

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Title: Effect of friction stir welding and self-ion irradiation on dispersoid evolution in oxide dispersion strengthened steel MA956 up to 25 dpa

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