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

Zhang, Dalong; Briggs, Samuel A.; Edmondson, Philip D.; Gussev, Maxim N.; Howard, Richard H.; Field, Kevin G.

doi:10.1016/j.jnucmat.2019.151784

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

DOI:https://doi.org/10.1016/j.jnucmat.2019.151784· OSTI ID:1659640

^[1]; Briggs, Samuel A. ^[2]; ^[3]; ^[3]; ^[3]; ^[3]

Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Oregon State Univ., Corvallis, OR (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

An advanced accident-tolerant FeCrAl alloy, C35 M (Fe–13Cr–10Al–1Mo, at %), and its laser-fusion weldments were studied after neutron irradiation up to 1.8 dpa at 357 °C to evaluate the radiation damage and α'-precipitation kinetics. Results show that the densities of α' in the fusion zone (FZ) and the heat-affected zone (HAZ) were only a third of that in the base material, i.e., 2.3 × 10²⁴m^-3. Here, density of dislocation loops in the FZ and HAZ were less than half of that in base material. The size of α' precipitates and the dislocation loops were found to be smaller in base material, compared to FZ and HAZ. The variances in microstructural response within the different regions were attributed to initial as-welded states of each region, indicating the impact of the pre-irradiation condition on radiation response in FeCrAl alloys.

View Accepted Manuscript (DOE)

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

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1659640

Alternate ID(s):: OSTI ID: 1614992
OSTI ID: 1564377
OSTI ID: 22886473

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: n/a Vol. 527; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (52)

Quantitative binomial distribution analyses of nanoscale like‐solute atom clustering and segregation in atom probe tomography data Moody, Michael P.; Stephenson, Leigh T.; Ceguerra, Anna V. Microscopy Research and Technique, Vol. 71, Issue 7 https://doi.org/10.1002/jemt.20582	journal	July 2008
The 885° f (475° c) embrittlement of ferritic stainless steels Grobner, P. J. Metallurgical Transactions, Vol. 4, Issue 1 https://doi.org/10.1007/BF02649625	journal	January 1973
Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy Unocic, Kinga A.; Yamamoto, Yukinori; Pint, Bruce A. Oxidation of Metals, Vol. 87, Issue 3-4 https://doi.org/10.1007/s11085-017-9745-1	journal	March 2017
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
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
The kinetics of precipitation from supersaturated solid solutions Lifshitz, I. M.; Slyozov, V. V. Journal of Physics and Chemistry of Solids, Vol. 19, Issue 1-2 https://doi.org/10.1016/0022-3697(61)90054-3	journal	April 1961
Ostwald ripening in multicomponent alloys Umantsev, A.; Olson, G. B. Scripta Metallurgica et Materialia, Vol. 29, Issue 8 https://doi.org/10.1016/0956-716X(93)90191-T	journal	October 1993
A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels Mathon, M. H.; de Carlan, Y.; Geoffroy, G. Journal of Nuclear Materials, Vol. 312, Issue 2-3 https://doi.org/10.1016/S0022-3115(02)01630-6	journal	February 2003
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
Al partitioning in MA 956, an ODS ferritic stainless steel Read, H. G.; Murakami, H.; Hono, K. Scripta Materialia, Vol. 36, Issue 3 https://doi.org/10.1016/S1359-6462(96)00388-0	journal	February 1997
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
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
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
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors George, Nathan Michael; Terrani, Kurt; Powers, Jeff Annals of Nuclear Energy, Vol. 75 https://doi.org/10.1016/j.anucene.2014.09.005	journal	January 2015
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part II: Irradiation induced hardening Pokor, C.; Brechet, Y.; Dubuisson, P. Journal of Nuclear Materials, Vol. 326, Issue 1 https://doi.org/10.1016/j.jnucmat.2003.12.008	journal	March 2004
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
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
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
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
Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction Farmer, M. T.; Leibowitz, L.; Terrani, K. A. Journal of Nuclear Materials, Vol. 448, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.12.022	journal	May 2014
Microstructural changes in a neutron-irradiated Fe–6 at.%Cr alloy Bachhav, Mukesh; Yao, Lan; Robert Odette, G. Journal of Nuclear Materials, Vol. 453, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.06.050	journal	October 2014
Microstructural changes in a neutron-irradiated Fe–15 at.%Cr alloy Bachhav, Mukesh; Robert Odette, G.; Marquis, Emmanuelle A. Journal of Nuclear Materials, Vol. 454, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.08.026	journal	November 2014
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
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
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
Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy Field, Kevin G.; Briggs, Samuel A.; Hu, Xunxiang Journal of Nuclear Materials, Vol. 483 https://doi.org/10.1016/j.jnucmat.2016.10.050	journal	January 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
Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels McMurray, J. W.; Hu, R.; Ushakov, S. V. Journal of Nuclear Materials, Vol. 492 https://doi.org/10.1016/j.jnucmat.2017.05.016	journal	August 2017
Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa Field, Kevin G.; Briggs, Samuel A.; Sridharan, Kumar Journal of Nuclear Materials, Vol. 495 https://doi.org/10.1016/j.jnucmat.2017.07.061	journal	November 2017
Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations Aydogan, E.; Weaver, J. S.; Maloy, S. A. Journal of Nuclear Materials, Vol. 503 https://doi.org/10.1016/j.jnucmat.2018.03.002	journal	May 2018
Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments Gussev, M. N.; Cakmak, E.; Field, K. G. Journal of Nuclear Materials, Vol. 504 https://doi.org/10.1016/j.jnucmat.2018.03.036	journal	June 2018
Role of refractory inclusions in the radiation-induced microstructure of APMT Zhang, Dalong; Briggs, Samuel A.; Field, Kevin G. Journal of Nuclear Materials, Vol. 505 https://doi.org/10.1016/j.jnucmat.2018.04.017	journal	July 2018
Characterizing nanoscale precipitation in a titanium alloy by laser-assisted atom probe tomography Coakley, James; Radecka, Anna; Dye, David Materials Characterization, Vol. 141 https://doi.org/10.1016/j.matchar.2018.04.016	journal	July 2018
Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys Gussev, M. N.; Field, K. G.; Yamamoto, Y. Materials & Design, Vol. 129 https://doi.org/10.1016/j.matdes.2017.05.009	journal	September 2017
Impact toughness of commercial and model FeCrAl alloys Sun, Zhiqian; Yamamoto, Yukinori; Chen, Xiang Materials Science and Engineering: A, Vol. 734 https://doi.org/10.1016/j.msea.2018.07.074	journal	September 2018
Applications of atom-probe tomography to the characterisation of solute behaviours Marquis, Emmanuelle A.; Hyde, Jonathan M. Materials Science and Engineering: R: Reports, Vol. 69, Issue 4-5 https://doi.org/10.1016/j.mser.2010.05.001	journal	July 2010
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
On the α–α′ miscibility gap of Fe–Cr alloys Bonny, G.; Terentyev, D.; Malerba, L. Scripta Materialia, Vol. 59, Issue 11 https://doi.org/10.1016/j.scriptamat.2008.08.008	journal	December 2008
Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys Kobayashi, Satoru; Takasugi, Takayuki Scripta Materialia, Vol. 63, Issue 11 https://doi.org/10.1016/j.scriptamat.2010.08.015	journal	November 2010
Influence of recrystallization on phase separation kinetics of oxide dispersion strengthened Fe–Cr–Al alloy Capdevila, C.; Miller, M. K.; Pimentel, G. Scripta Materialia, Vol. 66, Issue 5 https://doi.org/10.1016/j.scriptamat.2011.11.003	journal	March 2012
α′ precipitation in neutron-irradiated Fe–Cr alloys Bachhav, Mukesh; Robert Odette, G.; Marquis, Emmanuelle A. Scripta Materialia, Vol. 74 https://doi.org/10.1016/j.scriptamat.2013.10.001	journal	March 2014
Initial clustering – a key factor for phase separation kinetics in Fe–Cr-based alloys Zhou, Jing; Odqvist, Joakim; Höglund, Lars Scripta Materialia, Vol. 75 https://doi.org/10.1016/j.scriptamat.2013.11.020	journal	March 2014
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
Precipitation of α′ in neutron irradiated commercial FeCrAl alloys Field, Kevin G.; Littrell, Kenneth C.; Briggs, Samuel A. Scripta Materialia, Vol. 142 https://doi.org/10.1016/j.scriptamat.2017.08.022	journal	January 2018
Diffraction contrast STEM of dislocations: Imaging and simulations Phillips, P. J.; Brandes, M. C.; Mills, M. J. Ultramicroscopy, Vol. 111, Issue 9-10 https://doi.org/10.1016/j.ultramic.2011.07.001	journal	August 2011
Analysis of conventional and three‐dimensional atom probe data for multiphase materials Camus, Eric; Abromeit, Christian Journal of Applied Physics, Vol. 75, Issue 5 https://doi.org/10.1063/1.356258	journal	March 1994
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
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
The effect of alloying on 485°C embrittlement Courtnall, M.; Pickering, F. B. Metal Science, Vol. 10, Issue 8 https://doi.org/10.1179/030634576790432353	journal	August 1976
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

Similar Records

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

Journal Article · Sat Dec 14 23:00:00 EST 2019 · Journal of Nuclear Materials · OSTI ID:1614992

Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations

Journal Article · Thu Mar 01 23:00:00 EST 2018 · Journal of Nuclear Materials · OSTI ID:1425772

Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

Technical Report · Tue Aug 01 00:00:00 EDT 2017 · OSTI ID:1410934

Related Subjects

36 MATERIALS SCIENCE
Accident Tolerant
Dislocation Loops
FeCrAl
Precipitation
Welding

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

Citation Formats

References (52)

Similar Records

Related Subjects