Radiation instability of equal channel angular extruded T91 at ultra-high damage levels

Gigax, Jonathan G.; Kim, Hyosim; Chen, Tianyi; Garner, F. A.; Shao, Lin

doi:10.1016/j.actamat.2017.04.038

Radiation instability of equal channel angular extruded T91 at ultra-high damage levels

Journal Article · Tue Apr 18 00:00:00 EDT 2017 · Acta Materialia

DOI:https://doi.org/10.1016/j.actamat.2017.04.038· OSTI ID:1533475

Gigax, Jonathan G. ^[1]; Kim, Hyosim ^[2]; Chen, Tianyi ^[2]; Garner, F. A. ^[3]; ^[2]

Texas A & M Univ., College Station, TX (United States); DOE/OSTI
Texas A & M Univ., College Station, TX (United States)
Texas A & M Univ., College Station, TX (United States); Radiation Effects Consulting, Richland, WA (United States)

Although several studies have shown that nano-grained alloys have higher radiation resistance than coarse-grained variants, with dense grain boundary structures acting as defect sinks to remove damage, the present study shows the failure of severe deformation to suppress void swelling in T91 alloy at ultra-high damage levels. Fe self-ion irradiation up to 1000 peak dpa produced significantly more swelling in extruded T91 than conventional T91 at 475 °C. Dramatic radiation-enhanced grain growth was observed in the extruded T91, manifested in two rapid grain growth stages. One stage occurs at a relatively low damage level, and the other at a higher damage level beyond 750 peak dpa. The second rapid growth stage is correlated with void swelling and starts at the end of the swelling incubation period. The study suggests that the defect sink properties of the growing grain boundaries under a coarsening process are different from that of stable boundary configurations. When void swelling becomes significant and voids act as a biased sink for vacancies, the growing grain boundaries act as a biased sink for interstitials, leading to rapid growth at higher damage levels.

View Accepted Manuscript (DOE)

Research Organization:: Texas A & M Univ., College Station, TX (United States). Texas A & M Engineering Experiment Station

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

Grant/Contract Number:: NE0008297

OSTI ID:: 1533475

Alternate ID(s):: OSTI ID: 1550497
OSTI ID: 22695888

Journal Information:: Acta Materialia, Journal Name: Acta Materialia Journal Issue: C Vol. 132; ISSN 1359-6454

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
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