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Multiscale Modeling of Irradiation Induced Hardening in a-Fe, Fe-Cr and Fe-Ni Systems

Published online by Cambridge University Press:  01 February 2011

Ioannis Mastorakos ,
Ngoc Le ,
Melody Zeine ,
Hussein M Zbib  and
Moe Khaleel
Ioannis Mastorakos
Affiliation:
[email protected], Washington State University, School of Mechanical and Materials Engineering, Pullman, Washington, United States
Ngoc Le
Affiliation:
[email protected], Washington State University, School of Mechanical and Materials Engineering, Pullman, Washington, United States
Melody Zeine
Affiliation:
[email protected], Washington State University, School of Mechanical and Materials Engineering, Pullman, Washington, United States
Hussein M Zbib
Affiliation:
[email protected], Washington State University, Mechanical and Materials Engineering, Pullman, Washington, United States
Moe Khaleel
Affiliation:
[email protected], Pacific Northwest National Laboratory, Richland, Washington, United States
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Abstract

Structural materials in the new Generation IV reactors will operate in harsh radiation conditions coupled with high levels of hydrogen and helium production, thus experiencing severe degradation of mechanical properties. The development of structural materials for use in such a hostile environment is predicated on understanding the underlying physical mechanisms responsible for microstructural evolution along with corresponding dimensional instabilities and mechanical property changes. As the phenomena involved are very complex and span in several length scales, a multiscale approach is necessary in order to fully understand the degradation of materials in irradiated environments. The purpose of this work is to study the behavior of Fe systems (namely a-Fe, Fe-Cr and Fe-Ni) under irradiation using both Molecular Dynamics (MD) and Dislocation Dynamics (DD) simulations. Critical information is passed from the atomistic (MD) to the microscopic scale (DD) in order to study the degradation of the material under examination. In particular, information pertaining to the dislocation-defects (such as voids, helium bubbles and prismatic loops) interactions is obtained from MD simulations. Then this information is used by DD to simulate large systems with high dislocation and defect densities.

Keywords

radiation effectsFesimulation
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1264: Symposia Z/BB – Basic Actinide Science and Materials for Nuclear Applications , 2010 , 1264-BB06-05
Copyright
Copyright © Materials Research Society 2010

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References

1 Odette, G.R. Modeling Microstructural Evolution in Fusion-Reactor Environments. Journal of Nuclear Materials, 133, 127 (1985).Google Scholar
2 Spatig, P. et al. , Plastic flow properties and fracture toughness characterization of unirradiated and irradiated tempered martensitic steels. J. Nuc. Mater., 367–370, 527 (2007).Google Scholar
3http://lammps.sandia.gov/Google Scholar
4 Mendelev, M.I. et al. , Development of new interatomic potentials appropriate for crystalline and liquid iron, Phil. Mag. 83, 3977 (2003); G. Bonny et al., Fe-Ni many-body potential for metallurgical applications, Modelling Simul. Mater. Sci. Eng. 17, 025010 (2009).Google Scholar
5 Hirth, J.p. and Lothe, J. J., Theory of dislocations, Krieger Publ. Company, Malabar, 1982 Google Scholar
6 Zbib, H.M. and Rubia, T. Diaz de la, A multiscale model of plasticity, Int. J. Plasticity, 18, 1133 (2002).Google Scholar
7 Rhee, M. et al. , A Superdislocation Model for the Strengthening of Metal Matrix Composites and the Initiation and Propagation of Shear Bands, Acta Met. Mat., 42, 2645 (1994).Google Scholar