Hostname: page-component-78c5997874-8bhkd Total loading time: 0 Render date: 2024-11-19T12:09:03.100Z Has data issue: false hasContentIssue false
  • English
  • Français

Irradiation damage of single crystal, coarse-grained, and nanograined copper under helium bombardment at 450 °C

Published online by Cambridge University Press:  22 October 2013

Weizhong Han ,
E.G. Fu ,
Michael J. Demkowicz ,
Yongqiang Wang  and
Amit Misra
Weizhong Han*
Affiliation:
Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos, New Mexico 87545
E.G. Fu
Affiliation:
Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos, New Mexico 87545
Michael J. Demkowicz
Affiliation:
Department of Materials Science and Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139
Yongqiang Wang
Affiliation:
Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos, New Mexico 87545
Amit Misra
Affiliation:
Center for Integrated Nanotechnologies, Los Alamos National Laboratory, Los Alamos, New Mexico 87545
*
a)Address all correspondence to this author. e-mail: weizhong@lanl.gov
Get access

Abstract

The irradiation damage behaviors of single crystal (SC), coarse-grained (CG), and nanograined (NG) copper (Cu) films were investigated under Helium (He) ion implantation at 450 °C with different ion fluences. In irradiated SC films, plenty of cavities are nucleated, and some of them preferentially formed on growth defects or dislocation lines. In the irradiated CG Cu, cavities formed both in grain interior and along grain boundaries; obvious void-denuded zones can be identified near grain boundaries. In contrast, irradiation-induced cavities in NG Cu were observed mainly gathering along grain boundaries with much less cavities in the grain interiors. The grains in irradiated NG Cu are significantly coarsened. The number density and average radius of cavities in NG Cu was smaller than that in irradiated SC Cu and CG Cu. These experiments indicate that grain boundaries are efficient sinks for irradiation-induced vacancies and highlight the important role of reducing grain size in suppressing radiation-induced void swelling.

Keywords

cavityvoid-swellinggrain boundaryvoid-denuded zonesink efficiency
Type
Invited Feature Papers
Information
Journal of Materials Research , Volume 28 , Issue 20 , 28 October 2013 , pp. 2763 - 2770
Copyright
Copyright © Materials Research Society 2013 

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

Guerin, Y., Was, G.S., and Zinkle, S.J.: Materials challenges for advanced nuclear energy systems. MRS Bull. 34, 10 (2009).Google Scholar
Zinkle, S.J. and Busby, J.T.: Structural materials for fission & fusion energy. Mater. Today 12, 12 (2009).CrossRefGoogle Scholar
Odette, G.R. and Hoelzer, D.T.: Irradiation-tolerant nanostructured ferritic alloys: Transforming helium from a liability to an asset. JOM 62, 84 (2010).CrossRefGoogle Scholar
Mansur, L.K.: Void swelling in metals and alloys under irradiation-assessment of theory. Nucl. Technol. 40, 5 (1978).CrossRefGoogle Scholar
Trinkaus, H. and Wolfer, W.G.: Conditions for dislocation loop punching by helium bubbles. J. Nucl. Mater. 122, 522 (1984).CrossRefGoogle Scholar
Stubbins, J.F.: Void swelling and radiation-induced phase-transformation in high-purity Fe-Ni-Cr alloys. J. Nucl. Mater. 141–143, 748 (1986).CrossRefGoogle Scholar
Mansur, L.K.: Theory and experimental background on dimensional changes in irradiated alloys. J. Nucl. Mater. 216, 97 (1994).CrossRefGoogle Scholar
Singh, B.N., Foreman, A.J.E., and Trinkaus, H.: Radiation hardening revisited: Role of intracascade clustering. J. Nucl. Mater. 249, 103 (1997).CrossRefGoogle Scholar
Odette, G.R. and Lucas, G.E.: Recent progress in understanding reactor pressure vessel steel embrittlement. Radiat. Eff. Defects Solids 144, 189 (1998).CrossRefGoogle Scholar
Zinkle, S.J. and Ghoniem, N.M.: Operating temperature windows for fusion reactor structural materials. Fusion Eng. Des. 51–52, 55 (2000).CrossRefGoogle Scholar
Victoria, M., Baluc, N., Bailat, C., Dai, Y., Luppo, M.I., Schaublin, R., and Singh, B.N.: The microstructure and associated properties of irradiated fcc and bcc metals. J. Nucl. Mater. 276, 114 (2000).CrossRefGoogle Scholar
Diaz de la Rubia, T., Zbib, H.M., Khraishi, T.A., Wirth, B.D., Victoria, M., and Caturla, M.J.: Multiscale modeling of plastic flow localization in irradiated materials. Nature 406, 871 (2000).CrossRefGoogle Scholar
Odette, G.R. and Lucas, G.E.: Embrittlement of nuclear reactor pressure vessels. JOM 53, 18 (2001).CrossRefGoogle Scholar
Sickafus, K.E., Grimes, R.W., Valdez, J.A., Cleave, A., Tang, M., Ishimaru, M., Corish, S.M., Stanek, C.R., and Uberuaga, B.P.: Radiation-induced amorphization and radiation tolerance in structurally related oxides. Nat. Mater. 2, 217 (2007).CrossRefGoogle Scholar
Singh, B.N.: Effect of grain-size on void formation during high-energy electron-irradiation of austenitic stainless steel. Philos. Mag. 29, 25 (1974).CrossRefGoogle Scholar
Rose, M., Balogh, A.G., and Hahn, H.: Instability of irradiation induced defects in nanostructured materials. Nucl. Instrum. Methods Phys. Res., Sect. B 127–128, 119 (1997).CrossRefGoogle Scholar
Chimi, Y., Iwase, A., Ishikawa, N., Kobiyama, A., Inami, T., and Okuda, S.: Instability of irradiation induced defects in nanostructured materials. J. Nucl. Mater. 297, 255 (2001).Google Scholar
Nita, N., Schaeublin, R., Victoria, M., and Valiew, R.Z.: Effects of irradiation on the microstructure and mechanical properties of nanostructured materials. Philos. Mag. 85, 723 (2005).CrossRefGoogle Scholar
Shen, T.D., Feng, S., Tang, M., Valdez, J.A., Wang, Y., and Sickafus, K.E.: Enhanced radiation tolerance in nanocrystalline MgGa2O4. Appl. Phys. Lett. 90, 263115 (2007).CrossRefGoogle Scholar
Samaras, M., Derlet, P.M., Van Swygenhoven, H., and Victoria, M.: Computer simulation of displacement cascades in nanocrystalline Ni. Phys. Rev. Lett. 88, 125505 (2002).CrossRefGoogle ScholarPubMed
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 327, 1631 (2010).CrossRefGoogle ScholarPubMed
Misra, A., Demkowicz, M.J., Zhang, X., and Hoagland, R.G.: The radiation damage tolerance of ultra-high strength nanolayered composites. JOM 59, 62 (2007).CrossRefGoogle Scholar
Demkowicz, M.J., Hoagland, R.G., and Hirth, J.P.: Interface structure and radiation damage resistance in Cu-Nb multilayer nanocomposites. Phys. Rev. Lett. 136, 136102 (2008).CrossRefGoogle Scholar
Fu, E.G., Carter, J., Swadener, G., Misra, A., Shao, L., Wang, H., and Zhang, X.: Size dependent enhancement of helium ion irradiation tolerance in sputtered Cu/V nanolaminates. J. Nucl. Mater. 385, 629 (2009).CrossRefGoogle Scholar
Misra, A. and Thilly, L.: Structural metals at extremes. MRS Bull. 35, 965 (2010).Google Scholar
Swaminathan, N., Kamenski, P.J., Morgan, D., and Szlufarska, I.: Effect of grain size and grain boundaries on defect production in nanocrystalline 3C-SiC. Acta Mater. 58, 2843 (2010).CrossRefGoogle Scholar
Yang, Y., Huang, H.C., and Zinkle, S.J.: Anomaly in dependence of radiation-induced vacancy accumulation on grain size. J. Nucl. Mater. 405, 261 (2010).CrossRefGoogle Scholar
Wei, Q.M., Wang, Y.Q., Nastasi, M., and Misra, A.: Nucleation and growth of bubbles in He ion-implanted V/Ag multilayers. Philos. Mag. 91, 553 (2011).CrossRefGoogle Scholar
Zhang, Y.F., Huang, H.C., Millett, P.C., Tonks, M., and Wolf, D.: Atomistic study of grain boundary sink strength under prolonged electron irradiation. J. Nucl. Mater. 422, 69 (2012).CrossRefGoogle Scholar
Adamson, R.B., Bell, W.L., and Kelly, P.C.: Neutron irradiation effect of copper at 327°C. J. Nucl. Mater. 92, 149 (1980).CrossRefGoogle Scholar
Singh, B.N., Leffers, T., Green, W.V., and Victoria, M.: Grain boundary related effect in aluminum during 600Mev proton irradiation at different temperatures. J. Nucl. Mater. 122, 703 (1984).CrossRefGoogle Scholar
Dollar, M. and Gleiter, H.: Point-defect annihilation at grain boundaries in gold. Scr. Metall. 19, 481 (1985).CrossRefGoogle Scholar
Zinkle, S.J. and Sindelar, R.L.: Defect microstructures in neutron irradiated copper and stainless steel. J. Nucl. Mater. 155–157, 1196 (1988).CrossRefGoogle Scholar
Zinkle, S.J. and Farrell, K.: Void swelling and defect cluster formation in reactor irradiated copper. J. Nucl. Mater. 168, 262 (1989).CrossRefGoogle Scholar
Zinkle, S.J.: Microstructure of ion irradiated ceramic insulators. Nucl. Instrum. Methods Phys. Res., Sect. B 91, 234 (1994).CrossRefGoogle Scholar
Thorsen, P.A., Bilde-Sorensen, J.B., and Singh, B.N.: Bubble formation at grain boundaries in helium implanted copper. Scr. Mater. 51, 557 (2004).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
Was, G.S.: Fundamentals of Radiation Materials Science: Metals and Alloys (Springer, Berlin, 2007).Google Scholar
Johnson, P.B. and Mazey, D.J.: The gas-bubble superlatic and the development of surface structure in He+ and H+ irradiated metals at 300K. J. Nucl. Mater. 93, 721 (1980).CrossRefGoogle Scholar
Ziegler, J.F., Biersack, J.P., and Littmark, U.: The Stopping and Range of Ions in Solids (Pergamon Press, New York, 1985).Google Scholar
Williams, D.B. and Carter, C.B.: Transmission Electron Microscopy: A Text Book for Materials Science (Springer, New York, 1996).CrossRefGoogle Scholar
Glowinski, L.D., Fiche, C., and Lott, M.: Study on formation of cavities in copper irradiation with copper ions of 500 keV. J. Nucl. Mater. 47, 295 (1973).CrossRefGoogle Scholar
Glowinski, L.D. and Fiche, C.: Study on formation of irradiated voids in copper III irradiation with 500 keV copper ions and effect of implanted gases. J. Nucl. Mater. 61, 29 (1976).CrossRefGoogle Scholar
Zinkle, S.J. and Lee, E.H.: Effect of oxygen on vacancy cluster morphology in metals. Metall. Trans. A 21, 1037 (1990).CrossRefGoogle Scholar
Zinkle, S.J. and Farrell, K.: Microstructure and cavity swelling in reactor-irradiated dilute copper-boron alloy. J. Nucl. Mater. 179, 994 (1991).CrossRefGoogle Scholar
Singh, B.N. and Horsewell, A.: Effect of fission neutron and 600 MeV proton irradiations on microstructural evolution in OFHC copper. J. Nucl. Mater. 212, 410 (1994).CrossRefGoogle Scholar
Muroga, T., Watanabe, H., Yoshida, N., Kurishita, H., and Hamilton, M.L.: Microstructure and tensile properties of neutron irradiated Cu and Cu-5Ni containing isotopically controlled boron. J. Nucl. Mater. 225, 137 (1995).CrossRefGoogle Scholar
Muroga, T., Watanabe, H., and Yoshida, N.: Effect of solid transmutants and helium in copper studied by mixed-spectrum neutron irradiation. J. Nucl. Mater. 258, 955 (1998).CrossRefGoogle Scholar
Wang, P., Thompson, D.A., and Smeltzer, W.: Implantation and grain growth in Ni thin films induced by Bi and Ag ions. Nucl. Instrum. Methods Phys. Res., Sect. B 16, 288 (1986).CrossRefGoogle Scholar
Atwater, H.A., Thompson, C.V., and Smith, H.I.: Ion bombardment enhanced grain growth in germanium, silicon and gold thin films. J. Appl. Phys. 64, 2337 (1988).CrossRefGoogle Scholar
Alexander, D.E., Was, G.S., and Rehn, L.E.: The heat of mixing effect on ion induced grain growth. J. Appl. Phys. 70, 1252 (1991).CrossRefGoogle Scholar
Kaoumi, D., Motta, A.T., and Birtcher, R.C.: A thermal spike model of grain growth under irradiation. J. Appl. Phys. 104, 073525 (2008).CrossRefGoogle Scholar
Hishinuma, A., Katano, Y., and Shiraishi, K.: Surface effect on void swelling behavior of stainless steel. J. Nucl. Sci. Technol. 14, 664 (1977).CrossRefGoogle Scholar