Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys
Abstract
Recent irradiations of Ni-Fe concentrated solid solution alloys have demonstrated significant improvement of radiation performance. This improvement is attributed to redistribution of the alloying elements near sinks of point defects (voids, dislocations) due to chemically-biased atomic diffusion, where vacancies have preference to migrate via Fe atoms and interstitials via Ni atoms. In Ni-Fe, all sinks are enriched by Ni atoms, which strongly affects further interactions of radiation-produced mobile defects with voids and dislocations, hence void growth and dislocation climb. Ni-decorated sinks interact stronger with interstitial atoms than vacancies, which enhances dislocation loops growth. At the same time, Ni segregation creates Fe-enriched “channels” for vacancy migration out of the damage region to agglomerate in the outer regions, inaccessible to interstitial atoms. Furthermore, strong effect of chemically-biased diffusion is supported by transmission electron microscope characterization and calls for special attention in designing alloys with desired properties through tuning defect mobilities.
- Authors:
-
[2];
[2];
[2]
- Univ. of Michigan, Ann Arbor, MI (United States)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Energy Frontier Research Centers (EFRC) (United States). Energy Dissipation to Defect Evolution (EDDE); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1542244
- Alternate Identifier(s):
- OSTI ID: 1637016
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Current Opinion in Solid State and Materials Science
- Additional Journal Information:
- Journal Volume: 23; Journal Issue: 2; Journal ID: ISSN 1359-0286
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND SUPERFLUIDITY; 36 MATERIALS SCIENCE; Metallic alloys; Ni-Fe; Ion irradiation; Component segregation; Swelling
Citation Formats
Barashev, Alexander V., Osetsky, Yuri N., Bei, Hongbin, Lu, Chenyang, Wang, Lumin, and Zhang, Yanwen. Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys. United States: N. p., 2018.
Web. doi:10.1016/j.cossms.2018.12.001.
Barashev, Alexander V., Osetsky, Yuri N., Bei, Hongbin, Lu, Chenyang, Wang, Lumin, & Zhang, Yanwen. Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys. United States. https://doi.org/10.1016/j.cossms.2018.12.001
Barashev, Alexander V., Osetsky, Yuri N., Bei, Hongbin, Lu, Chenyang, Wang, Lumin, and Zhang, Yanwen. Mon .
"Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys". United States. https://doi.org/10.1016/j.cossms.2018.12.001. https://www.osti.gov/servlets/purl/1542244.
@article{osti_1542244,
title = {Chemically-biased diffusion and segregation impede void growth in irradiated Ni-Fe alloys},
author = {Barashev, Alexander V. and Osetsky, Yuri N. and Bei, Hongbin and Lu, Chenyang and Wang, Lumin and Zhang, Yanwen},
abstractNote = {Recent irradiations of Ni-Fe concentrated solid solution alloys have demonstrated significant improvement of radiation performance. This improvement is attributed to redistribution of the alloying elements near sinks of point defects (voids, dislocations) due to chemically-biased atomic diffusion, where vacancies have preference to migrate via Fe atoms and interstitials via Ni atoms. In Ni-Fe, all sinks are enriched by Ni atoms, which strongly affects further interactions of radiation-produced mobile defects with voids and dislocations, hence void growth and dislocation climb. Ni-decorated sinks interact stronger with interstitial atoms than vacancies, which enhances dislocation loops growth. At the same time, Ni segregation creates Fe-enriched “channels” for vacancy migration out of the damage region to agglomerate in the outer regions, inaccessible to interstitial atoms. Furthermore, strong effect of chemically-biased diffusion is supported by transmission electron microscope characterization and calls for special attention in designing alloys with desired properties through tuning defect mobilities.},
doi = {10.1016/j.cossms.2018.12.001},
journal = {Current Opinion in Solid State and Materials Science},
number = 2,
volume = 23,
place = {United States},
year = {2018},
month = {12}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Search WorldCat to find libraries that may hold this journal
Cited by: 6 works
Citation information provided by
Web of Science
Web of Science
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
Works referenced in this record:
Voids in Irradiated Stainless Steel
journal, November 1967
- Cawthorne, C.; Fulton, E. J.
- Nature, Vol. 216, Issue 5115
Influence of chemical disorder on energy dissipation and defect evolution in concentrated solid solution alloys
journal, October 2015
- Zhang, Yanwen; Stocks, G. Malcolm; Jin, Ke
- Nature Communications, Vol. 6, Issue 1
Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys
journal, December 2016
- Lu, Chenyang; Niu, Liangliang; Chen, Nanjun
- Nature Communications, Vol. 7, Issue 1
Atomic-level heterogeneity and defect dynamics in concentrated solid-solution alloys
journal, October 2017
- Zhang, Yanwen; Zhao, Shijun; Weber, William J.
- Current Opinion in Solid State and Materials Science, Vol. 21, Issue 5
The Dislocation Bias
journal, August 2007
- Wolfer, W. G.
- Journal of Computer-Aided Materials Design, Vol. 14, Issue 3
Production bias due to clustering of point defects in irradiation-induced cascades
journal, April 1992
- Woo, C. H.; Singh, B. N.
- Philosophical Magazine A, Vol. 65, Issue 4
Glide of interstitial loops produced under cascade damage conditions: Possible effects on void formation
journal, December 1992
- Trinkaus, H.; Singh, B. N.; Foreman, A. J. E.
- Journal of Nuclear Materials, Vol. 199, Issue 1
Segregation in irradiated alloys: The inverse Kirkendall effect and the effect of constitution on void swelling
journal, September 1978
- Marwick, A. D.
- Journal of Physics F: Metal Physics, Vol. 8, Issue 9
Solute segregation in vacancy gradients generated by sintering and temperature changes
journal, May 1969
- Anthony, T. R.
- Acta Metallurgica, Vol. 17, Issue 5
Segregation of alloying elements to free surfaces during irradiation
journal, September 1974
- Okamoto, P. R.; Wiedersich, H.
- Journal of Nuclear Materials, Vol. 53
Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys
journal, April 2017
- Lu, Chenyang; Yang, Taini; Jin, Ke
- Acta Materialia, Vol. 127
Swelling and radiation-induced segregation in austentic alloys
journal, June 2005
- Allen, T. R.; Cole, J. I.; Gan, J.
- Journal of Nuclear Materials, Vol. 342, Issue 1-3
An experimental survey of swelling in commercial Fe-Cr-Ni alloys bombarded with 5 MeV Ni Ions
journal, November 1974
- Johnston, W. G.; Rosolowski, J. H.; Turkalo, A. M.
- Journal of Nuclear Materials, Vol. 54, Issue 1
A theory of radiation-induced segregation in concentrated alloys
journal, August 1979
- Wiedersich, H.; Okamoto, P. R.; Lam, N. Q.
- Journal of Nuclear Materials, Vol. 83, Issue 1
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
Atomic displacements and defect accumulation during irradiation with energetic particles: An autobiographical review
journal, August 1999
- Singh, B. N.
- Radiation Effects and Defects in Solids, Vol. 148, Issue 1-4
Preferential diffusion in concentrated solid solution alloys: NiFe, NiCo and NiCoCr
journal, April 2017
- Zhao, Shijun; Osetsky, Yuri; Zhang, Yanwen
- Acta Materialia, Vol. 128
Specific features of defect and mass transport in concentrated fcc alloys
journal, August 2016
- Osetsky, Yuri N.; Béland, Laurent K.; Stoller, Roger E.
- Acta Materialia, Vol. 115
On the existence and origin of sluggish diffusion in chemically disordered concentrated alloys
journal, June 2018
- Osetsky, Yuri N.; Béland, Laurent K.; Barashev, Alexander V.
- Current Opinion in Solid State and Materials Science, Vol. 22, Issue 3
Effect of nickel on point defects diffusion in Fe – Ni alloys
journal, June 2017
- Anento, N.; Serra, A.; Osetsky, Y.
- Acta Materialia, Vol. 132
New ion beam materials laboratory for materials modification and irradiation effects research
journal, November 2014
- Zhang, Y.; Crespillo, M. L.; Xue, H.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 338
SRIM – The stopping and range of ions in matter (2010)
journal, June 2010
- Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
Interatomic potential to study plasticity in stainless steels: the FeNiCr model alloy
journal, November 2011
- Bonny, G.; Terentyev, D.; Pasianot, R. C.
- Modelling and Simulation in Materials Science and Engineering, Vol. 19, Issue 8
The role of nickel in radiation damage of ferritic alloys
journal, February 2015
- Osetsky, Y.; Anento, N.; Serra, A.
- Acta Materialia, Vol. 84
Relation between partial diffusion coefficients in alloys and their swelling behaviour under fast neutron irradiation
journal, June 1976
- Venker, H.; Ehrlich, K.
- Journal of Nuclear Materials, Vol. 60, Issue 3
Structure of Defect Cascades in Fast-Neutron-Irradiated Aluminum by Diffuse X-Ray Scattering
journal, January 1980
- Guérard, B. v.; Grasse, D.; Peisl, J.
- Physical Review Letters, Vol. 44, Issue 4
One-dimensional atomic transport by clusters of self-interstitial atoms in iron and copper
journal, January 2003
- Osetsky, Yu. N.; Bacon, D. J.; Serra, A.
- Philosophical Magazine, Vol. 83, Issue 1
Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations
journal, January 2018
- Zinkle, S. J.; Snead, L. L.
- Scripta Materialia, Vol. 143
Elemental inhomogeneities developed in stainless steels by radiation-induced segregation
journal, October 1993
- Kenik, Edward A.
- Journal of Nuclear Materials, Vol. 205
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys
journal, April 2011
- Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian
- Journal of Nuclear Materials, Vol. 411, Issue 1-3
Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory
journal, August 1978
- Mansur, L. K.
- Nuclear Technology, Vol. 40, Issue 1
An effect of solute segregation on void growth in irradiated dilute alloys
journal, April 1975
- Brailsford, A. D.
- Journal of Nuclear Materials, Vol. 56, Issue 1
The capture efficiency of coated voids
journal, July 1980
- Wolfer, W. G.; Mansur, L. K.
- Journal of Nuclear Materials, Vol. 91, Issue 2-3
Self-diffusion in austenitic Fe-Cr-Ni alloys
journal, March 1980
- Rothman, S. J.; Nowicki, L. J.; Murch, G. E.
- Journal of Physics F: Metal Physics, Vol. 10, Issue 3
Drift forces on vacancies and interstitials in alloys with radiation-induced segregation
journal, February 1983
- Wolfer, W. G.
- Journal of Nuclear Materials, Vol. 114, Issue 2-3
Simultaneous analysis of three-dimensional percolation models
journal, November 2013
- Xu, Xiao; Wang, Junfeng; Lv, Jian-Ping
- Frontiers of Physics, Vol. 9, Issue 1
Diffusion, correlation, and percolation in a random alloy
journal, January 1981
- Murch, G. E.; Rothman, S. J.
- Philosophical Magazine A, Vol. 43, Issue 1