Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy

Field, Kevin G.; Briggs, Samuel A.; Hu, Xunxiang; Yamamoto, Yukinori; Howard, Richard H.; Sridharan, Kumar

doi:10.1016/j.jnucmat.2016.10.050

Title: Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy

Journal Article · Tue Nov 01 00:00:00 EDT 2016 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2016.10.050· OSTI ID:1333089

^[1];

^[2]; Hu, Xunxiang ^[1]; Yamamoto, Yukinori ^[1];

^[1]; Sridharan, Kumar ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Wisconsin-Madison, Madison, WI (United States)

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.

View Accepted Manuscript (DOE)

View Accepted Manuscript (Publisher)

Cite

Export

Save

Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1333089

Alternate ID(s):: OSTI ID: 1414020

Journal Information:: Journal of Nuclear Materials, Vol. 483, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 37 works

Citation information provided by
Web of Science

References (48)

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors Yamamoto, Y.; Pint, B. A.; Terrani, K. A. Journal of Nuclear Materials, Vol. 467 https://doi.org/10.1016/j.jnucmat.2015.10.019	journal	December 2015
Accident tolerant fuels for LWRs: A perspective Zinkle, S. J.; Terrani, K. A.; Gehin, J. C. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.005	journal	May 2014
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments Pint, B. A.; Terrani, K. A.; Brady, M. P. Journal of Nuclear Materials, Vol. 440, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.05.047	journal	September 2013
Effect of steam on high temperature oxidation behaviour of alumina-forming alloys Pint, B. A.; Unocic, K. A.; Terrani, K. A. Materials at High Temperatures, Vol. 32, Issue 1-2 https://doi.org/10.1179/0960340914Z.00000000058	journal	January 2015
Uniform corrosion of FeCrAl alloys in LWR coolant environments Terrani, K. A.; Pint, B. A.; Kim, Y. -J. Journal of Nuclear Materials, Vol. 479 https://doi.org/10.1016/j.jnucmat.2016.06.047	journal	October 2016
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C. Journal of Nuclear Materials, Vol. 465 https://doi.org/10.1016/j.jnucmat.2015.06.023	journal	October 2015
Irradiation-enhanced α′ precipitation in model FeCrAl alloys Edmondson, P. D.; Briggs, S. A. Scripta Materialia, Vol. 116 https://doi.org/10.1016/j.scriptamat.2016.02.002	journal	April 2016
Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel Watanabe, S.; Takamatsu, Y.; Sakaguchi, N. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00204-X	journal	December 2000
Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel Duh, T. S.; Kai, J. J.; Chen, F. R. Journal of Nuclear Materials, Vol. 283-287 https://doi.org/10.1016/S0022-3115(00)00255-5	journal	December 2000
Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9wt.% Cr model ferritic/martensitic steel Field, Kevin G.; Miller, Brandon D.; Chichester, Heather J. M. Journal of Nuclear Materials, Vol. 445, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.056	journal	February 2014
Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe–Cr–Ni alloys Yang, Ying; Field, Kevin G.; Allen, Todd R. Journal of Nuclear Materials, Vol. 473 https://doi.org/10.1016/j.jnucmat.2016.02.007	journal	May 2016
Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments Field, Kevin G.; Yang, Ying; Allen, Todd R. Acta Materialia, Vol. 89 https://doi.org/10.1016/j.actamat.2015.01.064	journal	May 2015
Modeling radiation-induced segregation in austenitic Fe–Cr–Ni alloys Allen, T. R.; Was, G. S. Acta Materialia, Vol. 46, Issue 10 https://doi.org/10.1016/S1359-6454(98)00019-6	journal	June 1998
A systematic study of radiation-induced segregation in ferritic–martensitic alloys Wharry, Janelle P.; Was, Gary S. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.07.071	journal	November 2013
Modelling of grain boundary segregation, precipitation and precipitate-free zones of high strength aluminium alloys—I. The model Jiang, H.; Faulkner, R. G. Acta Materialia, Vol. 44, Issue 5 https://doi.org/10.1016/1359-6454(95)00317-7	journal	May 1996
Grain boundary segregation in neutron-irradiated 304 stainless steel studied by atom probe tomography Toyama, T.; Nozawa, Y.; Van Renterghem, W. Journal of Nuclear Materials, Vol. 425, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.11.072	journal	June 2012
On grain-size-dependent void swelling in pure copper irradiated with fission neutrons Singh, B. N.; Eldrup, M.; Zinkle, S. J. Philosophical Magazine A, Vol. 82, Issue 6 https://doi.org/10.1080/01418610208240021	journal	April 2002
Void denuded zone formation for Fe–15Cr–15Ni steel and PNC316 stainless steel under neutron and electron irradiations Sekio, Yoshihiro; Yamashita, Shinichiro; Sakaguchi, Norihito Journal of Nuclear Materials, Vol. 458 https://doi.org/10.1016/j.jnucmat.2014.12.054	journal	March 2015
Bubble nucleation in grain interior and its influence on helium accumulation at grain boundaries Foreman, A. J. E.; Singh, B. N. Journal of Nuclear Materials, Vol. 133-134 https://doi.org/10.1016/0022-3115(85)90187-4	journal	August 1985
Kinetics of the growth of helium bubbles at the grain boundaries. formation of the spatially inhomogeneous distribution of helium bubbles near the grain boundaries Ryazanov, A. I.; Arutyunova, G. A.; Manichev, V. M. Journal of Nuclear Materials, Vol. 135, Issue 2-3 https://doi.org/10.1016/0022-3115(85)90083-2	journal	October 1985
Thermal stability of radiation produced defects in molybdenum Brimhall, J. L.; Mastel, B.; Bierlein, T. K. Acta Metallurgica, Vol. 16, Issue 6 https://doi.org/10.1016/0001-6160(68)90096-5	journal	June 1968
Neutron irradiated molybdenum-relationship of microstructure to irradiation temperature Brimhall, J. L.; Mastel, B. Radiation Effects, Vol. 3, Issue 2 https://doi.org/10.1080/00337577008236275	journal	January 1970
Evolution of fine-scale defects in stainless steels neutron-irradiated at 275 °C Edwards, D. J.; Simonen, E. P.; Bruemmer, S. M. Journal of Nuclear Materials, Vol. 317, Issue 1 https://doi.org/10.1016/S0022-3115(03)00002-3	journal	April 2003
Heterogeneous dislocation formation and solute redistribution near grain boundaries in austenitic stainless steel under electron irradiation Sakaguchi, N.; Watanabe, S.; Takahashi, H. Acta Materialia, Vol. 49, Issue 7 https://doi.org/10.1016/S1359-6454(01)00031-3	journal	April 2001
Microstructure evolution of two model ferritic/martensitic steels under in situ ion irradiation at low doses (0–2dpa) Kaoumi, D.; Adamson, J.; Kirk, M. Journal of Nuclear Materials, Vol. 445, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.10.047	journal	February 2014
Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling Li, Meimei; Kirk, M. A.; Baldo, P. M. Philosophical Magazine, Vol. 92, Issue 16 https://doi.org/10.1080/14786435.2012.662601	journal	June 2012
Defect accumulation in pure fcc metals in the transient regime: a review Singh, B. N.; Zinkle, S. J. Journal of Nuclear Materials, Vol. 206, Issue 2-3 https://doi.org/10.1016/0022-3115(93)90125-I	journal	November 1993
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys Parish, Chad M.; Field, Kevin G.; Certain, Alicia G. Journal of Materials Research, Vol. 30, Issue 9 https://doi.org/10.1557/jmr.2015.32	journal	April 2015
Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature 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 https://doi.org/10.1016/j.nimb.2016.01.005	journal	March 2016
NIH Image to ImageJ: 25 years of image analysis Schneider, Caroline A.; Rasband, Wayne S.; Eliceiri, Kevin W. Nature Methods, Vol. 9, Issue 7 https://doi.org/10.1038/nmeth.2089	journal	June 2012
TEM characterization of dislocation loops in irradiated bcc Fe-based steels Yao, B.; Edwards, D. J.; Kurtz, R. J. Journal of Nuclear Materials, Vol. 434, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.12.002	journal	March 2013
Observation and analysis of defect cluster production and interactions with dislocations Zinkle, S. J.; Matsukawa, Y. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.298	journal	August 2004
Electron Radiation Damage of Iron in High Voltage Electron Microscope Yoshida, Naoaki; Kiritani, Michio; Eiichi Fujita, F. Journal of the Physical Society of Japan, Vol. 39, Issue 1 https://doi.org/10.1143/JPSJ.39.170	journal	July 1975
Radiation hardening in neutron-irradiated polycrystalline copper: Barrier strength of defect clusters Kojima, S.; Zinkle, S. J.; Heinisch, H. L. Journal of Nuclear Materials, Vol. 179-181 https://doi.org/10.1016/0022-3115(91)90255-6	journal	March 1991
Polycrystal orientation maps from TEM Fundenberger, J. -J.; Morawiec, A.; Bouzy, E. Ultramicroscopy, Vol. 96, Issue 2 https://doi.org/10.1016/S0304-3991(02)00435-7	journal	August 2003
The structure of high-angle grain boundaries Brandon, D. G. Acta Metallurgica, Vol. 14, Issue 11 https://doi.org/10.1016/0001-6160(66)90168-4	journal	November 1966
Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy Hu, Rong; Smith, George D. W.; Marquis, Emmanuelle A. Acta Materialia, Vol. 61, Issue 9 https://doi.org/10.1016/j.actamat.2013.02.043	journal	May 2013
Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel Field, Kevin G.; Barnard, Leland M.; Parish, Chad M. Journal of Nuclear Materials, Vol. 435, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.12.026	journal	April 2013
Effect of grain boundary character on sink efficiency Han, W. Z.; Demkowicz, M. J.; Fu, E. G. Acta Materialia, Vol. 60, Issue 18 https://doi.org/10.1016/j.actamat.2012.08.009	journal	October 2012
Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress Chen, J.; Jung, P.; Hoffelner, W. Acta Materialia, Vol. 56, Issue 2 https://doi.org/10.1016/j.actamat.2007.09.016	journal	January 2008
Behavior of ferritic/martensitic steels after n-irradiation at 200 and 300°C Matijasevic, M.; Lucon, E.; Almazouzi, A. Journal of Nuclear Materials, Vol. 377, Issue 1 https://doi.org/10.1016/j.jnucmat.2008.02.063	journal	June 2008
The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa Porollo, S. I.; Dvoriashin, A. M.; Vorobyev, A. N. Journal of Nuclear Materials, Vol. 256, Issue 2-3 https://doi.org/10.1016/S0022-3115(98)00043-9	journal	August 1998
Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses Yao, Z.; Hernández-Mayoral, M.; Jenkins, M. L. Philosophical Magazine, Vol. 88, Issue 21 https://doi.org/10.1080/14786430802380469	journal	July 2008
Microstructural examination of neutron-irradiated simple ferritic alloys Gelles, D. S. Journal of Nuclear Materials, Vol. 108-109 https://doi.org/10.1016/0022-3115(82)90523-2	journal	July 1982
Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA Katoh, Yutai; Kohyama, Akira; Gelles, David S. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(94)00669-5	journal	August 1995
Void-swelling in irons and ferritic steels Little, E. A.; Stow, D. A. Journal of Nuclear Materials, Vol. 87, Issue 1 https://doi.org/10.1016/0022-3115(79)90123-5	journal	November 1979
Effects of impurities on one-dimensional migration of interstitial clusters in iron under electron irradiation Satoh, Y.; Matsui, H.; Hamaoka, T. Physical Review B, Vol. 77, Issue 9 https://doi.org/10.1103/PhysRevB.77.094135	journal	March 2008
MD modeling of defects in Fe and their interactions Marian, Jaime; Wirth, Brian D.; Schäublin, Robin Journal of Nuclear Materials, Vol. 323, Issue 2-3 https://doi.org/10.1016/j.jnucmat.2003.08.037	journal	December 2003

Cited By (1)

Automated defect analysis in electron microscopic images Li, Wei; Field, Kevin G.; Morgan, Dane npj Computational Materials, Vol. 4, Issue 1 https://doi.org/10.1038/s41524-018-0093-8	journal	July 2018

Similar Records

Evaluation on the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys

Technical Report · Fri Sep 18 00:00:00 EDT 2015 · OSTI ID:1333089

Field, Kevin G.; Briggs, Samuel A.; Edmondson, Philip; +5 more

Influence of welding and neutron irradiation on dislocation loop formation and alpha' precipitation in a FeCrAl alloy

Journal Article · Sun Dec 15 00:00:00 EST 2019 · Journal of Nuclear Materials · OSTI ID:1333089

Zhang, Dalong; Briggs, Samuel A.; Edmondson, P D.; +3 more

Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy

Journal Article · Tue Sep 03 00:00:00 EDT 2019 · Journal of Nuclear Materials · OSTI ID:1333089

Zhang, Dalong; Briggs, Samuel A.; Edmondson, Philip D.; +3 more

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
FeCrAl
accident tolerant
phase stability
dislocation
grain boundary

Title: Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy

Citation Formats

References (48)

Cited By (1)

Similar Records

Related Subjects