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Grain boundary character dependence of radiation-induced segregation in a model Ni–Cr alloy

Published online by Cambridge University Press:  05 March 2015

Christopher M. Barr
Affiliation:
Department of Materials Science and Engineering, Drexel University, Philadelphia, Pennsylvania 19104, USA
Leland Barnard
Affiliation:
Department of Materials Science and Engineering, University of Wisconsin, Madison, Wisconsin 53706, USA
James E. Nathaniel
Affiliation:
Department of Materials Science and Engineering, Drexel University, Philadelphia, Pennsylvania 19104, USA
Khalid Hattar
Affiliation:
Radiation Solid-Interactions Group, Sandia National Laboratories, Albuquerque, New Mexico 87185, USA
Kinga A. Unocic
Affiliation:
Materials Science and Technology Division, Oak Ridge National Laboratories, Oak Ridge, Tennessee 37831, USA
Izabela Szlurfarska
Affiliation:
Department of Materials Science and Engineering, University of Wisconsin, Madison, Wisconsin 53706, USA; and Materials Science Program, University of Wisconsin, Madison, Wisconsin 53706, USA
Dane Morgan
Affiliation:
Department of Materials Science and Engineering, University of Wisconsin, Madison, Wisconsin 53706, USA; and Materials Science Program, University of Wisconsin, Madison, Wisconsin 53706, USA
Mitra L. Taheri
Affiliation:
Department of Materials Science and Engineering, Drexel University, Philadelphia, Pennsylvania 19104, USA
Corresponding
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Abstract

Ni-based fcc alloys are frequently used as critical structural materials in nuclear energy applications. Despite extensive studies, fundamental questions remain regarding point defect migration and solute segregation as a function of grain boundary character after irradiation. In this study, a coupled experimental and modeling approach is used to understand the response of grain boundary character in a model Ni–5Cr alloy after high temperature heavy-ion irradiation. Radiation-induced segregation and void denuded zones were experimentally examined as a function of grain boundary character, while a kinetic rate theory model with grain boundary character boundary conditions was used to theoretically model Cr depletion in the alloy system. The results highlight major variations in the radiation response between the coherent and incoherent twin grain boundaries, but show limited disparity in defect sink strength between random low- and high-angle grain boundary regimes.

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Copyright © Materials Research Society 2015 

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Footnotes

Contributing Editor: Joel Ribis

a)

This author was an editor of this focus issue during the review and decision stage. For the JMR policy on review and publication of manuscripts authored by editors, please refer to http://www.mrs.org/jmr-editor-manuscripts/.

References

Zinkle, S.J. and Was, G.S.: Materials challenges in nuclear energy. Acta Mater. 61, 735 (2013).CrossRefGoogle Scholar
Kenik, E.A. and Busby, J.T.: Radiation-induced degradation of stainless steel light water reactor internals. Mater. Sci. Eng., R 73, 67 (2012).CrossRefGoogle Scholar
Bruemmer, S.M., Simonen, E.P., Scott, P.M., Andresen, P.L., Was, G.S., and Nelson, J.L.: Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals. J. Nucl. Mater. 274, 299 (1999).CrossRefGoogle Scholar
Was, G.S., Wharry, J.P., Frisbie, B., Wirth, B.D., Morgan, D., Tucker, J.D., and Allen, T.R.: Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys. J. Nucl. Mater. 411, 41 (2011).CrossRefGoogle Scholar
Duh, T., Kai, J., and Chen, F.: Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel. J. Nucl. Mater. 287, 198 (2000).CrossRefGoogle Scholar
Kai, J.J., Chen, F.R., and Duh, T.S.: Effects of grain boundary misorientation on radiation-induced solute segregation in proton irradiated 304 stainless steels. Mater. Trans. 45, 40 (2004).CrossRefGoogle Scholar
Watanabe, S. and Takamatsu, Y.: Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel. J. Nucl. Mater. 287, 152 (2000).CrossRefGoogle Scholar
Sakaguchi, N., Endo, M., Watanabe, S., Kinoshita, H., Yamashita, S., and Kokawa, H.: Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel. J. Nucl. Mater. 434, 65 (2013).CrossRefGoogle Scholar
Demkowicz, M.J., Anderoglu, O., Zhang, X., and Misra, A.: The influence of Σ3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu. J. Mater. Res. 26, 1666 (2011).CrossRefGoogle Scholar
Li, N., Wang, J., Wang, Y.Q., Serruys, Y., Nastasi, M., and Misra, A.: Incoherent twin boundary migration induced by ion irradiation in Cu. J. Appl. Phys. 113, 023508 (2013).CrossRefGoogle Scholar
Li, N., Hattar, K., and Misra, A.: In situ probing of the evolution of irradiation-induced defects in copper. J. Nucl. Mater. 439, 185 (2013).CrossRefGoogle Scholar
Field, K.G., Barnard, L.M., Parish, C.M., Busby, J.T., Morgan, D., and Allen, T.R.: Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel. J. Nucl. Mater. 435, 172 (2013).CrossRefGoogle Scholar
Field, K.G., Miller, B.D., Chichester, H.J.M., Sridharan, K., and Allen, T.R.: Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9 wt.% Cr model ferritic/martensitic steel. J. Nucl. Mater. 445, 143 (2014).CrossRefGoogle Scholar
Barr, C.M., Vetterick, G.A., Unocic, K.A., Hattar, K., Bai, X.M., and Taheri, M.L.: Anisotropic radiation induced segregation in 316L austenitic stainless steel with grain boundary character. Acta Mater. 67, 145 (2014).CrossRefGoogle Scholar
Lee, G-G., Jin, H-H., Lee, Y-B., and Kwon, J.: Observation and rate theory modeling of grain boundary segregation in Σ3 twin boundaries in ion-irradiated stainless steel 316. J. Nucl. Mater. 449, 234 (2014).CrossRefGoogle Scholar
Han, W., Fu, E.G., Demkowicz, M.J., Wang, Y., and Misra, A.: Irradiation damage of single crystal, coarse-grained, and nanograined copper under helium bombardment at 450 °C. J. Mater. Res. 28, 2763 (2013).CrossRefGoogle Scholar
Han, W.Z., Demkowicz, M.J., Fu, E.G., Wang, Y.Q., and Misra, A.: Effect of grain boundary character on sink efficiency. Acta Mater. 60, 6341 (2012).CrossRefGoogle Scholar
Bai, X-M., Vernon, L., Hoagland, R., Voter, A., Nastasi, M., and Uberuaga, B.P.: Role of atomic structure on grain boundary-defect interactions in Cu. Phys. Rev. B. 85, 214103 (2012).CrossRefGoogle Scholar
Bai, X-M., Voter, A.F., Hoagland, R.G., Nastasi, M., and Uberuaga, B.P.: Efficient annealing of radiation damage near grain boundaries via interstitial emission. Science 80, 1631 (2010).CrossRefGoogle Scholar
Tschopp, M.A., Solanki, K., Gao, F., Sun, X., Khaleel, M., and Horstemeyer, M.: Probing grain boundary sink strength at the nanoscale: Energetics and length scales of vacancy and interstitial absorption by grain boundaries in α-Fe. Phys. Rev. B. 85, 1 (2012).CrossRefGoogle Scholar
Tschopp, M.A., Horstemeyer, M.F., Gao, F., Sun, X., and Khaleel, M.: Energetic driving force for preferential binding of self-interstitial atoms to Fe grain boundaries over vacancies. Scr. Mater. 64, 908 (2011).CrossRefGoogle Scholar
Barnard, L., Tucker, J.D., Choudhury, S., Allen, T.R., and Morgan, D.: Modeling radiation induced segregation in Ni–Cr model alloys from first principles. J. Nucl. Mater. 425, 8 (2012).CrossRefGoogle Scholar
Barnard, L. and Morgan, D.: Ab initio molecular dynamics simulation of interstitial diffusion in Ni–Cr alloys and implications for radiation induced segregation. J. Nucl. Mater. 449, 225 (2014).CrossRefGoogle Scholar
Tucker, J.D., Najafabadi, R., Allen, T.R., and Morgan, D.: Ab initio-based diffusion theory and tracer diffusion in Ni–Cr and Ni–Fe alloys. J. Nucl. Mater. 405, 216 (2010).CrossRefGoogle Scholar
Perks, J.M., Marwick, A.D., and English, C.A.: A Computer Code to Calculate Radiation-Induced Segregation in Concentrated Ternary Alloys, AERE-R-12121, 1986.Google Scholar
Allen, T.R. and Was, G.S.: Modeling radiation-induced segregation in austenitic Fe-Cr-Ni alloys. Acta Metall. 46, 3679 (1998).Google Scholar
Brandon, D.E.: The structure of high-angle grain boundaries. Acta Metall. 14, 1479 (1966).CrossRefGoogle Scholar
Randle, V.: A methodology for grain boundary plane assessment by single-section trace analysis. Scr. Mater. 44, 2789 (2001).CrossRefGoogle Scholar
Was, G.S. and Allen, T.: Intercomparison of microchemical evolution under various types of particle irradiation. J. Nucl. Mater. 205, 332 (1993).CrossRefGoogle Scholar
Stoller, R.E., Toloczko, M.B., Was, G.S., Certain, A.G., Dwaraknath, S., and Garner, F.A.: On the use of SRIM for computing radiation damage exposure. Nucl. Instrum. Methods Phys. Res., Sect. B 310, 75 (2013).CrossRefGoogle Scholar
Garner, F.A.: Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage. J. Nucl. Mater. 117, 177 (1983).CrossRefGoogle Scholar
Williams, D.B. and Carter, C.B.: The Transmission Electron Microscope. In Transmission Electron Microscopy: A Textbook for Materials Science. (Springer, 2009).CrossRefGoogle Scholar
Wiedersich, H., Okamoto, P.R.R., and Lam, N.Q.: A theory of radiation-induced segregation in concentrated alloys. J. Nucl. Mater. 83, 98 (1979).CrossRefGoogle Scholar
Duh, T., Kai, J., Chen, F., and Wang, L.: Numerical simulation modeling on the effects of grain boundary misorientation on radiation-induced solute segregation in 304 austenitic stainless steels. J. Nucl. Mater. 294, 267273 (2001).CrossRefGoogle Scholar
Ruzickova, J. and Million, B.: Self-diffusion of the components in the fcc phase of binary solid solutions of the Fe-Ni-Cr system. Mater. Sci. Eng. 50, 59 (1981).CrossRefGoogle Scholar
Ullmaier, H., Ehrhart, P., Jung, P., and Schultz, H.: Atomic Defects in Metals (Springer, Berlin, 1991).CrossRefGoogle Scholar
Tucker, J.D., Allen, T.R., Najafabadi, R., Allen, T.R., and Morgan, D.: Determination of solute-interstitial interactions in Ni-Cr by first principle. Int. Conf. Adv. Math. Comput. Methods React. Physics, M C, 2, 891 (2009).Google Scholar
Was, G.S.: Fundamentals of Radiation Materials Science: Metals and Alloys (Springer, Berlin, 2007).Google Scholar
Rittner, J.D. and Seidman, D.N.: <110> symmetric tilt grain-boundary structures in fcc metals with low stacking-fault energies. Phys. Rev. B 54, 6999 (1996).CrossRefGoogle Scholar
Olmsted, D.L., Foiles, S.M., and Holm, E.A.: Survey of computed grain boundary properties in face-centered cubic metals: I. Grain boundary energy. Acta Mater. 57, 3694 (2009).CrossRefGoogle Scholar
Yu, K.Y., Bufford, D., Khatkhatay, F., Wang, H., Kirk, M.A., and Zhang, X.: In situ studies of irradiation-induced twin boundary migration in nanotwinned Ag. Scr. Mater. 69, 385 (2013).CrossRefGoogle Scholar
Yu, K.Y., Bufford, D., Sun, C., Liu, Y., Wang, H., Kirk, M.A., Li, M., and Zhang, X.: Removal of stacking-fault tetrahedra by twin boundaries in nanotwinned metals. Nat. Commun. 4, 1377 (2013).CrossRefGoogle ScholarPubMed
Engler, O. and Randle, V.: Introduction to Texture Analysis, 2nd ed. (Taylor & Francis Group, Boca Raton, FL, 2010).Google Scholar
Priester, L.: Grain Boundaries: From Theory to Engineering, 1st ed. (Springer, New York, 2013).CrossRefGoogle Scholar
King, A.H. and Smith, D.A.: On the mechanisms of point-defect absorption by grain and twin boundaries. Philos. Mag. 42, 495 (1980).CrossRefGoogle Scholar
Burke, J. and Stuckey, D.: Dislocation loop-free zones around grain boundaries in quenched aluminium and aluminum alloys. Philos. Mag. 31, 1063 (1975).CrossRefGoogle Scholar
Basu, B.K. and Elbaum, C.: Surface vacancy pits and vacancy diffusion in aluminum. Acta Metall. 13, 1117 (1965).CrossRefGoogle Scholar
Siegel, R.W., Chang, S.M., and Balluffi, R.W.: Vacancy loss at grain boundaries in quenched polycrystalline gold. Acta Metall. 28, 249 (1979).CrossRefGoogle Scholar
Jiang, C., Swaminathan, N., Deng, J., Morgan, D., and Szlufarska, I.: Effect of grain boundary stresses on sink strength. Mater. Res. Lett. 2, 100 (2014).CrossRefGoogle Scholar

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