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Atomistic to Continuum Constitutive Modeling of Radiation Damage on FCC Metals and its Adaptation for the Generation of New Materials

Published online by Cambridge University Press:  10 March 2011

Shree Krishna  and
Suvranu De
Shree Krishna
Affiliation:
Department of Mechanical, Aerospace, and Nuclear Engineering Rensselaer Polytechnic Institute 110 8th St., Troy, NY 12180, USA Email: [email protected]; [email protected]
Suvranu De
Affiliation:
Department of Mechanical, Aerospace, and Nuclear Engineering Rensselaer Polytechnic Institute 110 8th St., Troy, NY 12180, USA Email: [email protected]; [email protected]
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Abstract

The paper presents a rate-independent dislocation growth and defect annihilation mechanism to capture the pre- and post-yield material behavior of FCC metals subjected to different doses of neutron radiation. Based on observation from molecular dynamics simulation and TEM experiments, the developed model is capable of capturing the salient features of irradiation induced hardening including increase in yield stress followed by yield drop and non-zero stress offset from the unirradiated stress-strain curve. The key contribution is a model for the critical resolved slip resistance that depends on both dislocation and defect densities which are governed by evolution equations based on physical observations. The result is an orientation-dependent nonhomogeneous deformation model which accounts for defect annihilation on active slip planes. Results for both single and polycrystalline simulations of OFHC copper are presented and are observed to be in reasonably good agreement with experimental data. Extension of the model to other FCC metals is straightforward and is currently being developed for BCC metals giving its way for generation of new materials.

Keywords

stress/strain relationshipradiation effectspolycrystal
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1298: Symposium Q/R/T – Advanced Materials for Applications in Extreme Environments , 2011 , mrsf10-1298-q11-03
Copyright
Copyright © Materials Research Society 2011

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References

REFERENCES

[1] Blewitt, T.H., Coltman, R.R., Jamison, R. E. and Redman, J.K., J. of Nuc. Mat. 2 (1960) p. 277.Google Scholar
[2] Robach, J.S., Robertson, I.M., Wirth, B. D. and Arsenlis, A., Phil. Mag. 83 (2003) p. 955 Google Scholar
[3] Arsenlis, A., Wirth, B. and Rhee, M., Phil. Mag. 84 (2004) p. 3617.Google Scholar
[4] Diaz de la, T. R., Zbib, H.M., Khraishi, T.A., Wirth, B.D., Victoria, M., caturla, M.J.. Nature 406 (2000) p. 871.Google Scholar
[5] Osetsky, Y.N., Stoller, R.E., Rodney, D. and Bacon, D.J.. Mat. Sci. and Engg. A. (2005) p. 370.Google Scholar
[6] Rodney, D., Martin, G. and Brechet, Y., Mater. Sci. Engg. A, 309–310 (2001) p.198.Google Scholar
[7] Singh, B.N., Edwards, D.J. and Toft, P., J. Nuc. Mater. 299 (2001) p. 205.Google Scholar
[8] Ghoniem, N., Tong, S., Singh, B.N., Phil. Mag. A 81(2001), p. 2743–2764.Google Scholar
[9] Wirth, B.D., Bulatov, V.V., and Diaz de la, T.R., J. Eng. Mater. Tecnol. 24 (2002) p. 329.Google Scholar
[10] Seeger, A., Proc.of the 2nd UN Int. Conf. on Atomic Energy, Geneva, UN, 1958, 250.Google Scholar
[11] Rice, J.R., J. Mech. Phys. Solids 19 (1971) p. 433.Google Scholar
[12] Essmann, U. and Rapp, M., Acta metall. 21 (1973) p. 1305.Google Scholar
[13] Arminjon, M., Textures and Microstructures, 14–18, (1991) p. 1121.Google Scholar
[14] Zamiri, A., Pourboghrat, F. and Barlat, F., Int. J. Plast. 23 (2007) p. 1126.Google Scholar
[15] Krishna, S., Zamiri, A., De, S., Phil. Mag. 90 (2010), p-4013 .Google Scholar