Numéro |
J. Phys. IV France
Volume 133, June 2006
|
|
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Page(s) | 805 - 809 | |
DOI | https://doi.org/10.1051/jp4:2006133162 | |
Publié en ligne | 16 juin 2006 |
J.-C. Gauthier, et al.
J. Phys. IV France 133 (2006) 805-809
DOI: 10.1051/jp4:2006133162
Radiation damage in metals, and amorphous silica in inertial fusion reactors: Modeling and experiments
J.M. Perlado1, 0, M. Victoria1, M.J. Caturla2, J. Marian3, M.L. Gámez4, C. Arévalo1, E. Martínez1, F. Mota1, M. Velarde1, G. Velarde1 and P. Cepas11 Instituto de Fusión Nuclear, Universidad Politécnica de Madrid, Spain
2 Department of Applied Physics, Universidad de Alicante, Spain
3 Lawrence Livermore National Laboratory, Livermore CA, USA
4 Department of Applied Physics, ETSII, Universidad Politécnica de Madrid, Madrid, Spain
Abstract
A systematic analysis of primary damage will follow for high-energy
recoils, in order to get distribution of cascades and subcascades
versus recoil energies. Considering Fe, simulations have been
performed using new activation energies for diffusion of
interstitial defects, and a new random 3D movement has been
considered in modeling. New vacancy's migration energies for 3-4
vacancy clusters and last ab-initio diffusion
parameters for impurities were also implemented. Results will be
compared to experiments, to quantify the defect concentration and
the defect type. A new full scale of irradiation experiments of
metals and diagnosis including resistivity analysis will also be
presented. In addition, the plans to extend such defect dynamics
simulation to the scale of defect-dislocation dynamics will be
presented. Using defect energetic and cascade damage obtained from
molecular dynamics, results will be presented on irradiation of hcp
-Zr under different conditions with a kinetic Monte Carlo
model. Cascades of 25 keV will be considered in the evolution of the
microstructure during irradiation under environment conditions of
600K, 10 - 6 dpa/s and 0.5 dpa. We will present preliminary
comparisons with experimental data. Finally, our previous and
present results on
-Zr will be extrapolated to Titanium
that has very useful applications in nuclear fusion reactors.
Defects in silica and carbon may be present in the material, in many
cases associated to impurities, or generated by irradiation. A
systematic identification of defect types in these materials,
depending on its final potential energy and its morphology,
calculating the co-ordination and neighbour type will be presented,
and their concentration as a function of stoichiometric deviations
is studied using classical molecular dynamic. To study the effects
of different hydrogen isotopes in silica and their interaction with
the defect concentration is considered as an important effect and a
modelling analysis will be presented. A full-scale experimental
program, using visible and infrared optical spectroscopy, for
understanding those mechanisms and validate simulation results will
also be presented.
© EDP Sciences 2006