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Title: Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Abstract

The development and understanding of the mechanical properties of neutron-irradiated FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature for nuclear reactor applications. This study focuses on the mechanical properties of model FeCrAl alloys and of a commercial FeCrAl alloy neutron-irradiated to up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382 °C. Tensile tests were completed at room temperature and at 320 °C, and a subset of fractured tensile specimens was examined by scanning electron microscopy. Results showed typical radiation hardening and embrittlement indicative of high chromium ferritic alloys with strong chromium composition dependencies at lower doses. At and above 7.0 dpa, the mechanical properties saturated for both the commercial and model FeCrAl alloys, although brittle cleavage fracture was observed at the highest dose in the model FeCrAl alloy with the highest chromium content (18 wt %). Finally, the results suggest the composition and microstructure of FeCrAl alloys plays a critical role in the mechanical response of FeCrAl alloys irradiated near temperatures relevant to light water reactors.

Authors:
ORCiD logo [1]; ORCiD logo [2];  [2]; ORCiD logo [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Univ. of Wisconsin, Madison, WI (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1351763
Alternate Identifier(s):
OSTI ID: 1419551
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 489; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; FeCrAl; accident tolerant; mechanical properties

Citation Formats

Field, Kevin G., Briggs, Samuel A., Sridharan, Kumar, Howard, Richard H., and Yamamoto, Yukinori. Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.03.038.
Field, Kevin G., Briggs, Samuel A., Sridharan, Kumar, Howard, Richard H., & Yamamoto, Yukinori. Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys. United States. doi:10.1016/j.jnucmat.2017.03.038.
Field, Kevin G., Briggs, Samuel A., Sridharan, Kumar, Howard, Richard H., and Yamamoto, Yukinori. Tue . "Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys". United States. doi:10.1016/j.jnucmat.2017.03.038. https://www.osti.gov/servlets/purl/1351763.
@article{osti_1351763,
title = {Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys},
author = {Field, Kevin G. and Briggs, Samuel A. and Sridharan, Kumar and Howard, Richard H. and Yamamoto, Yukinori},
abstractNote = {The development and understanding of the mechanical properties of neutron-irradiated FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature for nuclear reactor applications. This study focuses on the mechanical properties of model FeCrAl alloys and of a commercial FeCrAl alloy neutron-irradiated to up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382 °C. Tensile tests were completed at room temperature and at 320 °C, and a subset of fractured tensile specimens was examined by scanning electron microscopy. Results showed typical radiation hardening and embrittlement indicative of high chromium ferritic alloys with strong chromium composition dependencies at lower doses. At and above 7.0 dpa, the mechanical properties saturated for both the commercial and model FeCrAl alloys, although brittle cleavage fracture was observed at the highest dose in the model FeCrAl alloy with the highest chromium content (18 wt %). Finally, the results suggest the composition and microstructure of FeCrAl alloys plays a critical role in the mechanical response of FeCrAl alloys irradiated near temperatures relevant to light water reactors.},
doi = {10.1016/j.jnucmat.2017.03.038},
journal = {Journal of Nuclear Materials},
number = C,
volume = 489,
place = {United States},
year = {Tue Mar 28 00:00:00 EDT 2017},
month = {Tue Mar 28 00:00:00 EDT 2017}
}

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