Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

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

doi:10.1016/j.jnucmat.2017.07.061

Title: Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

Journal Article · Tue Aug 01 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.07.061· OSTI ID:1407805

^[1];

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

^[1]; Howard, Richard H. ^[1]

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

FeCrAl alloys with varying compositions and microstructures are under consideration for accident-tolerant fuel cladding, but limited details exist on dislocation loop formation and growth for this class of alloys under neutron irradiation. Four model FeCrAl alloys with chromium contents ranging from 10.01 to 17.51 wt % and alunimum contents of 4.78 to 2.93 wt % were neutron irradiated to doses of 0.3–0.8 displacements per atom (dpa) at temperatures of 335–355°C. On-zone STEM imaging revealed a mixed population of black dots and larger dislocation loops with either a/2< 111 > or a< 100 > Burgers vectors. Weak composition dependencies were observed and varied depending on whether the defect size, number density, or ratio of defect types was of interest. Here, the results were found to mirror those of previous studies on FeCrAl and FeCr alloys irradiated under similar conditions, although distinct differences exist.

View Accepted Manuscript (DOE)

View Accepted Manuscript (Publisher)

Cite

Export

Save

Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

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

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1407805

Alternate ID(s):: OSTI ID: 1495576

Journal Information:: Journal of Nuclear Materials, Vol. 495, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

Citation Metrics:

Cited by: 34 works

Citation information provided by
Web of Science

References (29)

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding Terrani, K. A.; Zinkle, S. J.; Snead, L. L. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.06.041	journal	May 2014
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
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
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys Briggs, Samuel A.; Edmondson, Philip D.; Littrell, Kenneth C. Acta Materialia, Vol. 129 https://doi.org/10.1016/j.actamat.2017.02.077	journal	May 2017
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys Field, Kevin G.; Briggs, Samuel A.; Sridharan, Kumar Journal of Nuclear Materials, Vol. 489 https://doi.org/10.1016/j.jnucmat.2017.03.038	journal	June 2017
Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys Haley, Jack C.; Briggs, Samuel A.; Edmondson, Philip D. Acta Materialia, Vol. 136 https://doi.org/10.1016/j.actamat.2017.07.011	journal	September 2017
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
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
Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing Gussev, Maxim N.; Howard, Richard H.; Terrani, Kurt A. Nuclear Engineering and Design, Vol. 320 https://doi.org/10.1016/j.nucengdes.2017.06.008	journal	August 2017
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
Orientation relationships and interface structure of α′-Cr nanoclusters embedded in α-Fe matrix after α–α′ demixing in neutron irradiated Oxide Dispersion Strengthened material Ribis, J.; Lozano-Perez, S. Materials Letters, Vol. 74 https://doi.org/10.1016/j.matlet.2012.01.115	journal	May 2012
Void-swelling in irons and ferritic steels Little, E. A. Journal of Nuclear Materials, Vol. 87, Issue 1 https://doi.org/10.1016/0022-3115(79)90122-3	journal	November 1979
Transmission electron microscopy investigation of the microstructure of Fe–Cr alloys induced by neutron and ion irradiation at 300 °C Hernández-Mayoral, M.; Heintze, C.; Oñorbe, E. Journal of Nuclear Materials, Vol. 474 https://doi.org/10.1016/j.jnucmat.2016.03.002	journal	June 2016
Effect of Cr on the mechanical properties and microstructure of Fe–Cr model alloys after n-irradiation Matijasevic, M.; Almazouzi, A. Journal of Nuclear Materials, Vol. 377, Issue 1 https://doi.org/10.1016/j.jnucmat.2008.02.061	journal	June 2008
Post-irradiation deformation in a Fe-9%Cr alloy Gelles, D. S.; Schäublin, R. E. Materials Science and Engineering: A, Vol. 309-310 https://doi.org/10.1016/S0921-5093(00)01772-X	journal	July 2001
Mechanisms of radiation strengthening in Fe–Cr alloys as revealed by atomistic studies Terentyev, D.; Bonny, G.; Domain, C. Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.03.054	journal	November 2013
Assessment of hardening due to dislocation loops in bcc iron: Overview and analysis of atomistic simulations for edge dislocations Bonny, G.; Terentyev, D.; Elena, J. Journal of Nuclear Materials, Vol. 473 https://doi.org/10.1016/j.jnucmat.2016.02.031	journal	May 2016
Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys Bergner, F.; Pareige, C.; Hernández-Mayoral, M. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.01.024	journal	May 2014
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
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
Neutron irradiation effects in Fe and Fe-Cr at 300 °C Chen, Wei-Ying; Miao, Yinbin; Gan, Jian Acta Materialia, Vol. 111 https://doi.org/10.1016/j.actamat.2016.03.060	journal	June 2016
The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures Yao, Z.; Jenkins, M. L.; Hernández-Mayoral, M. Philosophical Magazine, Vol. 90, Issue 35-36 https://doi.org/10.1080/14786430903430981	journal	December 2010
Solving the Puzzle of $⟨ 100 ⟩$ Interstitial Loop Formation in bcc Iron Xu, Haixuan; Stoller, Roger E.; Osetsky, Yury N. Physical Review Letters, Vol. 110, Issue 26 https://doi.org/10.1103/PhysRevLett.110.265503	journal	June 2013

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

Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

Journal Article · Sun Feb 21 00:00:00 EST 2021 · Journal of Nuclear Materials · OSTI ID:1407805

Massey, Caleb P.; Zhang, Dalong; Briggs, Samuel A.; +4 more

Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys

Journal Article · Thu Jul 06 00:00:00 EDT 2017 · Acta Materialia · OSTI ID:1407805

Haley, Jack C.; Briggs, Samuel A.; Edmondson, Philip D.; +4 more

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:1407805

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

Related Subjects

36 MATERIALS SCIENCE
FeCrAl
Accident tolerant
Dislocation
Radiation effects

Title: Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

Citation Formats

References (29)

Cited By (1)

Similar Records

Related Subjects