Mechanisms of radiation-induced segregation around He bubbles in a Fe-Cr-Ni crystal

Kombaiah, Boopathy; Edmondson, Philip D.; Wang, Yongqiang; Boatner, Lynn A.; Zhang, Yanwen

doi:10.1016/j.jnucmat.2018.11.030

Title: Mechanisms of radiation-induced segregation around He bubbles in a Fe-Cr-Ni crystal

Journal Article · 21 November 2018 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2018.11.030 · OSTI ID:1488728

^[1];

^[1]; Wang, Yongqiang ^[2];

^[1];

^[3]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)

We report that Fe-15Cr-15Ni (wt.%) austenitic stainless steel was irradiated with 200 keV ⁴He⁺ ions to a fluence of 5 × 10¹⁶/cm² at 500 °C. Radiation-induced segregation (RIS) at He bubbles in the irradiated steel was measured using Energy Dispersive X-ray Spectroscopy (EDS) coupled with Scanning Transmission Electron Microscopy (STEM). The RIS measurements exhibited an enrichment of Ni and a depletion of Cr and Fe at the bubbles. To determine the underlying mechanisms of the RIS, the prediction of the Marwick model was compared with the RIS measurements. The model with parametric input in accordance with the Inverse Kirkendall effect (IKE), i.e. a preferential flux of elements associated with vacancy flux, was inadequate in explaining the observed amount of segregation of Fe, Cr and Ni. More specifically, a considerably lower ratio of the concentration gradient between Cr and Fe, $$\left(\frac{∇Cr}{∇Fe}\right)$$, of 0.53 was obtained from the RIS measurements versus the model-predicted value of 2.3, indicating an overestimation of Cr depletion at the bubbles by the Marwick model. To explain this difference between the model prediction and the RIS measurements, in addition to the Cr depletion at the bubbles by IKE due to the fastest diffusion via vacancy flux, a preferential interstitial flux of Cr from the matrix to the bubbles is discussed as a possible concurrently operating mechanism.

View Accepted Manuscript (DOE)

Cite

Export

Save

Research Organization:: Energy Frontier Research Centers (EFRC) (United States). Energy Dissipation to Defect Evolution (EDDE); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES); USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)

Grant/Contract Number:: 89233218CNA000001; AC05-00OR22725

OSTI ID:: 1488728

Report Number(s):: LA-UR-19-30504

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 514; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (33)

The Dislocation Bias Wolfer, W. G. Journal of Computer-Aided Materials Design, Vol. 14, Issue 3 https://doi.org/10.1007/s10820-007-9051-3	journal	August 2007
Segregation of alloying elements to free surfaces during irradiation Okamoto, P. R.; Wiedersich, H. Journal of Nuclear Materials, Vol. 53 https://doi.org/10.1016/0022-3115(74)90267-0	journal	September 1974
Radiation-induced segregation in binary and ternary alloys Okamoto, P. R.; Rehn, L. E. Journal of Nuclear Materials, Vol. 83, Issue 1 https://doi.org/10.1016/0022-3115(79)90587-7	journal	August 1979
Compositional changes in Fe-Cr-Ni alloys under proton bombardment at elevated temperatures Lam, N. Q. Journal of Nuclear Materials, Vol. 117 https://doi.org/10.1016/0022-3115(83)90015-6	journal	July 1983
Mechanisms of helium interaction with radiation effects in metals and alloys: A review Mansur, L. K.; Coghlan, W. A. Journal of Nuclear Materials, Vol. 119, Issue 1 https://doi.org/10.1016/0022-3115(83)90047-8	journal	November 1983
Drift forces on vacancies and interstitials in alloys with radiation-induced segregation Wolfer, W. G. Journal of Nuclear Materials, Vol. 114, Issue 2-3 https://doi.org/10.1016/0022-3115(83)90268-4	journal	February 1983
Calculation of bias due to solute redistribution in an irradiated binary alloy: Surfaces of a thin foil Marwick, A. D. Journal of Nuclear Materials, Vol. 135, Issue 1 https://doi.org/10.1016/0022-3115(85)90438-6	journal	September 1985
Radiation-induced segregation in ion-irradiated stainless steels — The origin of compositional fluctuations in irradiated alloys Shepherd, C. M. Journal of Nuclear Materials, Vol. 175, Issue 3 https://doi.org/10.1016/0022-3115(90)90202-X	journal	December 1990
Theoretical basis for unified analysis of experimental data and design of swelling-resistant alloys Mansur, L. K.; Lee, E. H. Journal of Nuclear Materials, Vol. 179-181 https://doi.org/10.1016/0022-3115(91)90023-Z	journal	March 1991
Void bias factors due to the anisotropy of the point defect diffusion Borodin, V. A.; Ryazanov, A. I.; Abromeit, C. Journal of Nuclear Materials, Vol. 207 https://doi.org/10.1016/0022-3115(93)90266-2	journal	December 1993
Dependence of radiation-induced segregation on dose, temperature and alloy composition in austenitic alloys Damcott, D. L.; Allen, T. R.; Was, G. S. Journal of Nuclear Materials, Vol. 225 https://doi.org/10.1016/0022-3115(94)00690-3	journal	August 1995
Discriminant of RIS in multi-component alloys Watanabe, S.; Takahashi, H. Journal of Nuclear Materials, Vol. 208, Issue 1-2 https://doi.org/10.1016/0022-3115(94)90211-9	journal	January 1994
On the mechanism of radiation-induced segregation Watanabe, S.; Sakaguchi, N.; Kurome, K. Journal of Nuclear Materials, Vol. 240, Issue 3 https://doi.org/10.1016/S0022-3115(96)00710-6	journal	February 1997
On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys Allen, T. R.; Busby, J. T.; Was, G. S. Journal of Nuclear Materials, Vol. 255, Issue 1 https://doi.org/10.1016/S0022-3115(98)00010-5	journal	May 1998
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
Materials challenges in nuclear energy Zinkle, S. J.; Was, G. S. Acta Materialia, Vol. 61, Issue 3 https://doi.org/10.1016/j.actamat.2012.11.004	journal	February 2013
Effect of saddle point anisotropy of point defects on their absorption by dislocations and cavities Carpentier, D.; Jourdan, T.; Le Bouar, Y. Acta Materialia, Vol. 136 https://doi.org/10.1016/j.actamat.2017.07.013	journal	September 2017
Radiation-induced solute segregation in metallic alloys Ardell, Alan J.; Bellon, Pascal Current Opinion in Solid State and Materials Science, Vol. 20, Issue 3 https://doi.org/10.1016/j.cossms.2015.11.001	journal	June 2016
Cryo-quenched Fe-Ni-Cr alloy single crystals: A new decorative steel Boatner, L. A.; Kolopus, J. A.; Lavrik, Nicolay V. Journal of Alloys and Compounds, Vol. 691 https://doi.org/10.1016/j.jallcom.2016.08.327	journal	January 2017
Modeling of radiation-induced segregation at grain boundaries in Fe–Cr–Ni alloys Stepanov, I. A.; Pechenkin, V. A.; Konobeev, Yu. V. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.259	journal	August 2004
Structural materials for Gen-IV nuclear reactors: Challenges and opportunities Murty, K. L.; Charit, I. Journal of Nuclear Materials, Vol. 383, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2008.08.044	journal	December 2008
Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys Tucker, J. D.; Najafabadi, R.; Allen, T. R. Journal of Nuclear Materials, Vol. 405, Issue 3 https://doi.org/10.1016/j.jnucmat.2010.08.003	journal	October 2010
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.01.031	journal	April 2011
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
SRIM – The stopping and range of ions in matter (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 https://doi.org/10.1016/j.nimb.2010.02.091	journal	June 2010
On the use of SRIM for computing radiation damage exposure Stoller, R. E.; Toloczko, M. B.; Was, G. S. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 310 https://doi.org/10.1016/j.nimb.2013.05.008	journal	September 2013
Influence of chemical disorder on energy dissipation and defect evolution in concentrated solid solution alloys Zhang, Yanwen; Stocks, G. Malcolm; Jin, Ke Nature Communications, Vol. 6, Issue 1 https://doi.org/10.1038/ncomms9736	journal	October 2015
Defect energetics of concentrated solid-solution alloys from ab initio calculations: Ni _0.5 Co _0.5 , Ni _0.5 Fe _0.5 , Ni _0.8 Fe _0.2 and Ni _0.8 Cr _0.2 Zhao, Shijun; Stocks, G. Malcolm; Zhang, Yanwen Physical Chemistry Chemical Physics, Vol. 18, Issue 34 https://doi.org/10.1039/C6CP05161H	journal	January 2016
Stress−induced diffusion of point defects to spherical sinks Wolfer, W. G.; Ashkin, M. Journal of Applied Physics, Vol. 46, Issue 2 https://doi.org/10.1063/1.321679	journal	February 1975
Void Swelling in Electron Irradiated High Purity Fe-Cr-Ni Austenitic Alloys Hishinuma, Akimichi; Katano, Yoshio; Shiraishi, Kensuke Journal of Nuclear Science and Technology, Vol. 15, Issue 9 https://doi.org/10.1080/18811248.1978.9735572	journal	September 1978
Self-diffusion in austenitic Fe-Cr-Ni alloys Rothman, S. J.; Nowicki, L. J.; Murch, G. E. Journal of Physics F: Metal Physics, Vol. 10, Issue 3 https://doi.org/10.1088/0305-4608/10/3/009	journal	March 1980
Quantitative X-ray microanalysis of thin specimens in the transmission electron microscope; a review Lorimer, G. W. Mineralogical Magazine, Vol. 51, Issue 359 https://doi.org/10.1180/minmag.1987.051.359.05	journal	March 1987
Influence of Silicon and Phosphorus on Radiation-Induced Segregation of Chromium and Nickel in Austenitic Model Alloys Sakaguchi, Norihito; Takahashi, Heishichiro; Ichinose, Hideki MATERIALS TRANSACTIONS, Vol. 46, Issue 3 https://doi.org/10.2320/matertrans.46.440	journal	January 2005

Cited By (1)

Swelling and Helium Bubble Morphology in a Cryogenically Treated FeCrNi Alloy with Martensitic Transformation and Reversion after Helium Implantation Zhang, Feifei; Boatner, Lynn; Zhang, Yanwen Materials, Vol. 12, Issue 17 https://doi.org/10.3390/ma12172821	journal	September 2019

Similar Records

Feasibility of a novel approach for fast, economical determination of radiation damage in nuclear reactor cores. Final report, November 1, 1992--October 31, 1996

Technical Report · 1997 · OSTI ID:510543

Was, G S

Role of interstitial and interstitial-impurity interaction on irradiation-induced segregation in austenitic steels

Book · 1998 · OSTI ID:323490

Nastar, M; Martin, G; Bellon, P; +1 more

Radiation-induced grain boundary segregation in proton irradiated austenitic iron- and nickel-base alloys

Book · 1995 · OSTI ID:203769

Allen, T R; Damcott, D L; Was, G S; +1 more

Related Subjects

36 MATERIALS SCIENCE
material science

Title: Mechanisms of radiation-induced segregation around He bubbles in a Fe-Cr-Ni crystal

Citation Formats

References (33)

Cited By (1)

Similar Records

Related Subjects