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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]

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.
Authors:
 [1] ;  [2] ;  [3] ;  [3] ;  [3] ;  [1]
  1. Univ. of Michigan, Ann Arbor, MI (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States); Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Univ. of California, Santa Barbara, CA (United States)
Publication Date:
Report Number(s):
INL/JOU-17-42566-Rev000
Journal ID: ISSN 0022-3115
Grant/Contract Number:
AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 500; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; atom probe tomography; Fe-Cr; irradiation
OSTI Identifier:
1476820

Reese, Elaina R., Bachhav, Mukesh, Wells, Peter, Yamamoto, Takuya, Odette, G. Robert, and Marquis, Emmanuelle A.. 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]. United States: N. p., Web. doi:10.1016/j.jnucmat.2017.12.036.
Reese, Elaina R., Bachhav, Mukesh, Wells, Peter, Yamamoto, Takuya, Odette, G. Robert, & Marquis, Emmanuelle A.. 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]. United States. doi:10.1016/j.jnucmat.2017.12.036.
Reese, Elaina R., Bachhav, Mukesh, Wells, Peter, Yamamoto, Takuya, Odette, G. Robert, and Marquis, Emmanuelle A.. 2017. "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]". United States. doi:10.1016/j.jnucmat.2017.12.036. https://www.osti.gov/servlets/purl/1476820.
@article{osti_1476820,
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]},
author = {Reese, Elaina R. and Bachhav, Mukesh and Wells, Peter and Yamamoto, Takuya and Odette, G. Robert and Marquis, Emmanuelle A.},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2017.12.036},
journal = {Journal of Nuclear Materials},
number = C,
volume = 500,
place = {United States},
year = {2017},
month = {12}
}