Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
Abstract
FeCrAl alloys are an attractive materials class for nuclear power applications due to their increased environmental compatibility over more traditional nuclear materials. Preliminary studies into the radiation tolerance of FeCrAl alloys under accelerated neutron testing between 300-400 °C have shown post-irradiation microstructures containing dislocation loops and Cr-rich ' phase. Although these initial works established the post-irradiation microstructures, little to no focus was applied towards the influence of pre-irradiation microstructures on this response. Here, a well annealed commercial FeCrAl alloy, Alkrothal 720, was neutron irradiated to 1.8 dpa at 382 °C and then the role of random high angle grain boundaries on the spatial distribution and size of dislocation loops, dislocation loops, and black dot damage was analyzed using on-zone scanning transmission electron microscopy. Results showed a clear heterogeneous dislocation loop formation with dislocation loops showing an increased number density and size, black dot damage showing a significant number density decrease, and an increased size of dislocation loops in the vicinity directly adjacent to the grain boundary. Lastly, these results suggest the importance of the pre-irradiation microstructure on the radiation tolerance of FeCrAl alloys.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Univ. of Wisconsin-Madison, 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); USDOE Office of Science (SC), Basic Energy Sciences (BES)
- OSTI Identifier:
- 1333089
- Alternate Identifier(s):
- OSTI ID: 1414020
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 483; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 36 MATERIALS SCIENCE; FeCrAl; accident tolerant; phase stability; dislocation; grain boundary
Citation Formats
Field, Kevin G., Briggs, Samuel A., Hu, Xunxiang, Yamamoto, Yukinori, Howard, Richard H., and Sridharan, Kumar. Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy. United States: N. p., 2016.
Web. doi:10.1016/j.jnucmat.2016.10.050.
Field, Kevin G., Briggs, Samuel A., Hu, Xunxiang, Yamamoto, Yukinori, Howard, Richard H., & Sridharan, Kumar. Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy. United States. https://doi.org/10.1016/j.jnucmat.2016.10.050
Field, Kevin G., Briggs, Samuel A., Hu, Xunxiang, Yamamoto, Yukinori, Howard, Richard H., and Sridharan, Kumar. Tue .
"Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy". United States. https://doi.org/10.1016/j.jnucmat.2016.10.050. https://www.osti.gov/servlets/purl/1333089.
@article{osti_1333089,
title = {Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy},
author = {Field, Kevin G. and Briggs, Samuel A. and Hu, Xunxiang and Yamamoto, Yukinori and Howard, Richard H. and Sridharan, Kumar},
abstractNote = {FeCrAl alloys are an attractive materials class for nuclear power applications due to their increased environmental compatibility over more traditional nuclear materials. Preliminary studies into the radiation tolerance of FeCrAl alloys under accelerated neutron testing between 300-400 °C have shown post-irradiation microstructures containing dislocation loops and Cr-rich ' phase. Although these initial works established the post-irradiation microstructures, little to no focus was applied towards the influence of pre-irradiation microstructures on this response. Here, a well annealed commercial FeCrAl alloy, Alkrothal 720, was neutron irradiated to 1.8 dpa at 382 °C and then the role of random high angle grain boundaries on the spatial distribution and size of dislocation loops, dislocation loops, and black dot damage was analyzed using on-zone scanning transmission electron microscopy. Results showed a clear heterogeneous dislocation loop formation with dislocation loops showing an increased number density and size, black dot damage showing a significant number density decrease, and an increased size of dislocation loops in the vicinity directly adjacent to the grain boundary. Lastly, these results suggest the importance of the pre-irradiation microstructure on the radiation tolerance of FeCrAl alloys.},
doi = {10.1016/j.jnucmat.2016.10.050},
journal = {Journal of Nuclear Materials},
number = C,
volume = 483,
place = {United States},
year = {Tue Nov 01 00:00:00 EDT 2016},
month = {Tue Nov 01 00:00:00 EDT 2016}
}
Web of Science
Works referenced in this record:
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015
- Yamamoto, Y.; Pint, B. A.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 467
Accident tolerant fuels for LWRs: A perspective
journal, May 2014
- Zinkle, S. J.; Terrani, K. A.; Gehin, J. C.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
journal, September 2013
- Pint, B. A.; Terrani, K. A.; Brady, M. P.
- Journal of Nuclear Materials, Vol. 440, Issue 1-3
Effect of steam on high temperature oxidation behaviour of alumina-forming alloys
journal, January 2015
- Pint, B. A.; Unocic, K. A.; Terrani, K. A.
- Materials at High Temperatures, Vol. 32, Issue 1-2
Uniform corrosion of FeCrAl alloys in LWR coolant environments
journal, October 2016
- Terrani, K. A.; Pint, B. A.; Kim, Y. -J.
- Journal of Nuclear Materials, Vol. 479
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015
- Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C.
- Journal of Nuclear Materials, Vol. 465
Irradiation-enhanced α′ precipitation in model FeCrAl alloys
journal, April 2016
- Edmondson, P. D.; Briggs, S. A.
- Scripta Materialia, Vol. 116
Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel
journal, December 2000
- Watanabe, S.; Takamatsu, Y.; Sakaguchi, N.
- Journal of Nuclear Materials, Vol. 283-287
Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel
journal, December 2000
- Duh, T. S.; Kai, J. J.; Chen, F. R.
- Journal of Nuclear Materials, Vol. 283-287
Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9wt.% Cr model ferritic/martensitic steel
journal, February 2014
- Field, Kevin G.; Miller, Brandon D.; Chichester, Heather J. M.
- Journal of Nuclear Materials, Vol. 445, Issue 1-3
Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe–Cr–Ni alloys
journal, May 2016
- Yang, Ying; Field, Kevin G.; Allen, Todd R.
- Journal of Nuclear Materials, Vol. 473
Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments
journal, May 2015
- Field, Kevin G.; Yang, Ying; Allen, Todd R.
- Acta Materialia, Vol. 89
Modeling radiation-induced segregation in austenitic Fe–Cr–Ni alloys
journal, June 1998
- Allen, T. R.; Was, G. S.
- Acta Materialia, Vol. 46, Issue 10
A systematic study of radiation-induced segregation in ferritic–martensitic alloys
journal, November 2013
- Wharry, Janelle P.; Was, Gary S.
- Journal of Nuclear Materials, Vol. 442, Issue 1-3
Modelling of grain boundary segregation, precipitation and precipitate-free zones of high strength aluminium alloys—I. The model
journal, May 1996
- Jiang, H.; Faulkner, R. G.
- Acta Materialia, Vol. 44, Issue 5
Grain boundary segregation in neutron-irradiated 304 stainless steel studied by atom probe tomography
journal, June 2012
- Toyama, T.; Nozawa, Y.; Van Renterghem, W.
- Journal of Nuclear Materials, Vol. 425, Issue 1-3
On grain-size-dependent void swelling in pure copper irradiated with fission neutrons
journal, April 2002
- Singh, B. N.; Eldrup, M.; Zinkle, S. J.
- Philosophical Magazine A, Vol. 82, Issue 6
Void denuded zone formation for Fe–15Cr–15Ni steel and PNC316 stainless steel under neutron and electron irradiations
journal, March 2015
- Sekio, Yoshihiro; Yamashita, Shinichiro; Sakaguchi, Norihito
- Journal of Nuclear Materials, Vol. 458
Bubble nucleation in grain interior and its influence on helium accumulation at grain boundaries
journal, August 1985
- Foreman, A. J. E.; Singh, B. N.
- Journal of Nuclear Materials, Vol. 133-134
Kinetics of the growth of helium bubbles at the grain boundaries. formation of the spatially inhomogeneous distribution of helium bubbles near the grain boundaries
journal, October 1985
- Ryazanov, A. I.; Arutyunova, G. A.; Manichev, V. M.
- Journal of Nuclear Materials, Vol. 135, Issue 2-3
Thermal stability of radiation produced defects in molybdenum
journal, June 1968
- Brimhall, J. L.; Mastel, B.; Bierlein, T. K.
- Acta Metallurgica, Vol. 16, Issue 6
Neutron irradiated molybdenum-relationship of microstructure to irradiation temperature
journal, January 1970
- Brimhall, J. L.; Mastel, B.
- Radiation Effects, Vol. 3, Issue 2
Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C
journal, April 2003
- Edwards, D. J.; Simonen, E. P.; Bruemmer, S. M.
- Journal of Nuclear Materials, Vol. 317, Issue 1
Heterogeneous dislocation formation and solute redistribution near grain boundaries in austenitic stainless steel under electron irradiation
journal, April 2001
- Sakaguchi, N.; Watanabe, S.; Takahashi, H.
- Acta Materialia, Vol. 49, Issue 7
Microstructure evolution of two model ferritic/martensitic steels under in situ ion irradiation at low doses (0–2dpa)
journal, February 2014
- Kaoumi, D.; Adamson, J.; Kirk, M.
- Journal of Nuclear Materials, Vol. 445, Issue 1-3
Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling
journal, June 2012
- Li, Meimei; Kirk, M. A.; Baldo, P. M.
- Philosophical Magazine, Vol. 92, Issue 16
Defect accumulation in pure fcc metals in the transient regime: a review
journal, November 1993
- Singh, B. N.; Zinkle, S. J.
- Journal of Nuclear Materials, Vol. 206, Issue 2-3
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
journal, April 2015
- Parish, Chad M.; Field, Kevin G.; Certain, Alicia G.
- Journal of Materials Research, Vol. 30, Issue 9
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature
journal, March 2016
- Campbell, Anne A.; Porter, Wallace D.; Katoh, Yutai
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 370
NIH Image to ImageJ: 25 years of image analysis
journal, June 2012
- Schneider, Caroline A.; Rasband, Wayne S.; Eliceiri, Kevin W.
- Nature Methods, Vol. 9, Issue 7
TEM characterization of dislocation loops in irradiated bcc Fe-based steels
journal, March 2013
- Yao, B.; Edwards, D. J.; Kurtz, R. J.
- Journal of Nuclear Materials, Vol. 434, Issue 1-3
Observation and analysis of defect cluster production and interactions with dislocations
journal, August 2004
- Zinkle, S. J.; Matsukawa, Y.
- Journal of Nuclear Materials, Vol. 329-333
Electron Radiation Damage of Iron in High Voltage Electron Microscope
journal, July 1975
- Yoshida, Naoaki; Kiritani, Michio; Eiichi Fujita, F.
- Journal of the Physical Society of Japan, Vol. 39, Issue 1
Radiation hardening in neutron-irradiated polycrystalline copper: Barrier strength of defect clusters
journal, March 1991
- Kojima, S.; Zinkle, S. J.; Heinisch, H. L.
- Journal of Nuclear Materials, Vol. 179-181
Polycrystal orientation maps from TEM
journal, August 2003
- Fundenberger, J. -J.; Morawiec, A.; Bouzy, E.
- Ultramicroscopy, Vol. 96, Issue 2
The structure of high-angle grain boundaries
journal, November 1966
- Brandon, D. G.
- Acta Metallurgica, Vol. 14, Issue 11
Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy
journal, May 2013
- Hu, Rong; Smith, George D. W.; Marquis, Emmanuelle A.
- Acta Materialia, Vol. 61, Issue 9
Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel
journal, April 2013
- Field, Kevin G.; Barnard, Leland M.; Parish, Chad M.
- Journal of Nuclear Materials, Vol. 435, Issue 1-3
Effect of grain boundary character on sink efficiency
journal, October 2012
- Han, W. Z.; Demkowicz, M. J.; Fu, E. G.
- Acta Materialia, Vol. 60, Issue 18
Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress
journal, January 2008
- Chen, J.; Jung, P.; Hoffelner, W.
- Acta Materialia, Vol. 56, Issue 2
Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300°C
journal, June 2008
- Matijasevic, M.; Lucon, E.; Almazouzi, A.
- Journal of Nuclear Materials, Vol. 377, Issue 1
The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa
journal, August 1998
- Porollo, S. I.; Dvoriashin, A. M.; Vorobyev, A. N.
- Journal of Nuclear Materials, Vol. 256, Issue 2-3
Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses
journal, July 2008
- Yao, Z.; Hernández-Mayoral, M.; Jenkins, M. L.
- Philosophical Magazine, Vol. 88, Issue 21
Microstructural examination of neutron-irradiated simple ferritic alloys
journal, July 1982
- Gelles, D. S.
- Journal of Nuclear Materials, Vol. 108-109
Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA
journal, August 1995
- Katoh, Yutai; Kohyama, Akira; Gelles, David S.
- Journal of Nuclear Materials, Vol. 225
Void-swelling in irons and ferritic steels
journal, November 1979
- Little, E. A.; Stow, D. A.
- Journal of Nuclear Materials, Vol. 87, Issue 1
Effects of impurities on one-dimensional migration of interstitial clusters in iron under electron irradiation
journal, March 2008
- Satoh, Y.; Matsui, H.; Hamaoka, T.
- Physical Review B, Vol. 77, Issue 9
MD modeling of defects in Fe and their interactions
journal, December 2003
- Marian, Jaime; Wirth, Brian D.; Schäublin, Robin
- Journal of Nuclear Materials, Vol. 323, Issue 2-3
Works referencing / citing this record:
Automated defect analysis in electron microscopic images
journal, July 2018
- Li, Wei; Field, Kevin G.; Morgan, Dane
- npj Computational Materials, Vol. 4, Issue 1