Influence of processing on the microstructure and mechanical properties of 14YWT

Hoelzer, David T.; Unocic, Kinga A.; Sokolov, Mikhail A.; Byun, Thak Sang

doi:10.1016/j.jnucmat.2015.12.011

Influence of processing on the microstructure and mechanical properties of 14YWT

Journal Article · Tue Dec 15 00:00:00 EST 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2015.12.011· OSTI ID:1241464

Hoelzer, David T. ^[1]; Unocic, Kinga A. ^[1]; Sokolov, Mikhail A. ^[1]; Byun, Thak Sang ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

In this study, the investigation of the mechanical alloying (MA) conditions for producing the advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy led to significant improvements in balancing the strength, ductility and fracture toughness properties while still maintaining the salient microstructural features consisting of ultra-fine grains and high concentration of Y-, Ti- and O-enriched nanoclusters. The implemented changes to the processing conditions included reducing the contamination of the powder during ball milling, applying a pre-extrusion annealing treatment on the ball milled powder and exploring different extrusion temperatures at 850 °C (SM170 heat), 1000 °C (SM185) and 1150 °C (SM200). The microstructural studies of the three 14YWT heats showed similarities in the dispersion of nanoclusters and sub-micron size grains, indicating the microstructure was insensitive to the different extrusion conditions. Compared to past 14YWT heats, the three new heats showed lower strength, but higher ductility levels between 25 and 800 °C and significantly higher fracture toughness values between 25 °C and 700 °C. The lower contamination levels of O, C and N achieved with improved ball milling conditions plus the slightly larger grain size were identified as important factors for improving the balance in mechanical properties of the three heats of 14YWT.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1241464

Alternate ID(s):: OSTI ID: 1327106
OSTI ID: 22590293
OSTI ID: 1252041

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 471; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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