On α' precipitate composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys [On α' composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys]

Reese, Elaina R.; Bachhav, Mukesh; Wells, Peter; Yamamoto, Takuya; Odette, G. Robert; Marquis, Emmanuelle A.

doi:10.1016/j.jnucmat.2017.12.036

Title: On α' precipitate composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys [On α' composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys]

Journal Article · Thu Dec 28 00:00:00 EST 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.12.036· OSTI ID:1476820

Reese, Elaina R. ^[1]; Bachhav, Mukesh ^[2]; Wells, Peter ^[3]; Yamamoto, Takuya ^[3]; Odette, G. Robert ^[3]; Marquis, Emmanuelle A. ^[1]

Univ. of Michigan, Ann Arbor, MI (United States)
Univ. of Michigan, Ann Arbor, MI (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
Univ. of California, Santa Barbara, CA (United States)

Ferritic-martensitic steels are a leading candidate for many nuclear energy applications. However, precipitation of nanoscale a’ precipitates during thermal aging at temperatures above 450 °C, or during neutron irradiation at lower temperatures, makes these Fe-Cr steels susceptible to embrittlement. To complement the existing literature, a series of Fe-9 to 18 Cr alloys were neutron-irradiated at temperatures between 320 and 455 °C up to fluences of 20 dpa. In addition, post-irradiation annealing treatments at 500 and 600 °C were performed on the neutron-irradiated Fe-18 Cr alloy to validate the a-a’ phase boundaries. The microstructures were characterized using atom probe tomography and the results were analyzed in light of the existing literature. In conclusion, under neutron irradiation and thermal annealing, the measured a’ concentrations ranged from ~81 to 96 at.% Cr, which were discussed in terms of temperature, precipitate size, technique artefacts, and, possibly, cascade ballistic mixing.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

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

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1476820

Alternate ID(s):: OSTI ID: 1548859

Report Number(s):: INL/JOU-17-42566-Rev000

Journal Information:: Journal of Nuclear Materials, Vol. 500, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 44 works

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