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Mechanical Behavior of Ion-Irradiated Fe-Cr alloys Investigated by Spherical Indentation

Published online by Cambridge University Press:  10 February 2012

Christopher D. Hardie
Affiliation:
Department of Materials, University of Oxford, Oxford, OX1 3PH, United Kingdom
Steve G. Roberts
Affiliation:
Department of Materials, University of Oxford, Oxford, OX1 3PH, United Kingdom
Andrew J. Bushby
Affiliation:
School of Engineering and Materials Science, Queen Mary University of London, London, E1 4NS, United Kingdom
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Abstract

Fe12%Cr was irradiated with 2MeV and 0.5MeV Fe+ ions at 320°C, to create a layer with a mean level of displacement damage of 6.18dpa to a depth of ∼800nm. Spherical indentation, with a nominal tip radius of 10μm, was used to investigate the mechanical properties of the damage layer. Indents produced with loads of 2mN, 3mN, 5mN and 10mN were cross-sectioned and fabricated into TEM foils using an in situ lift-out technique in a dual beam FIB-SEM microscope. The extent of the plastic zone beneath the indent was observed in the TEM for each indentation. The indentation results were analysed so as to give an indentation stress-strain curve, in which strain softening was found to occur beyond the yield point. At loads up to 3mN the plastic zone remained entirely within the damage layer, implying strain-softening of the damaged material. At higher indentation loads the plastic zone was observed to extend into the softer un-irradiated substrate, giving rise to a further fall in flow stress with increasing strain.

Type
Research Article
Copyright
Copyright © Materials Research Society 2012

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References

REFERENCES

[1] Nix, W.D., Gao, H., Indentation size effects in crystalline materials: A law for strain gradient plasticity, J. Mech. Phys. Solids. 46 (1998) 411425.Google Scholar
[2] Pharr, G.M., Oliver, W.C., Measurement of thin film mechanical properties using nanoindentation. MRS Bulletin. 17 (1992) 2833.Google Scholar
[3] Hamilton, M.L., Gelles, D.S., Gardner, P.L., Post-irradiation deformation behavior in ferritic Fe–Cr alloys, in: Kumar, A.S., Gelles, D.S., Nanstad, R., Little, E.A. (Eds.), Sixteenth International Symposium on Effects of Radiation on Materials, ASTM STP 1175, 1st ed., ASTM, Philadelphia, 1993.Google Scholar
[4] Bushby, A.J., Roberts, S.G., Hardie, C.D., Nanoindentation investigation of ion-irradiated Fe–Cr alloys using spherical indenters, J. Mater. Res., 27, (2012), 8590.Google Scholar
[5] Ziegler, J.F., Ziegler, M.D., Biersack, J.P., SRIM – The stopping and range of ions in matter (2010), Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 268 (2010) 1818–1823.Google Scholar
[6] Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation, ASTM International. ASTM E521–96 (2009).Google Scholar
[7] Zhu, T.T., Bushby, A.J., Dunstan, D.J., Size effect in the initiation of plasticity for ceramics in nanoindentation, J. Mech. Phys. Solids. 56 (2008) 11701185.Google Scholar
[8] Langford, R.M., Clinton, C., In situ lift-out using a FIB-SEM system, Micron. 35 (2004) 607611.Google Scholar
[9] Bacon, D.J., Osetsky, Y.N., Rong, Z., Computer simulation of reactions between an edge dislocation and glissile self-interstitial clusters in iron, Philosophical Magazine. 86 (2006) 39213936.Google Scholar