ISOCHRONAL ANNEALING OF ELECTRON-IRRADIATED TUNGSTEN MODELLED BY CD METHOD: INFLUENCE OF CARBON ON THE FIRST AND SECOND STAGES OF RECOVERING

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Published: квіт. 9, 2018
Keywords:
Post-irradiation Annealing, Tungsten, Carbon Effect, Cluster Dynamics

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A. R. Gokhman
Південноукраїнський національний педагогічний університет імені К. Д. Ушинського
D. Terentyev
Nuclear Material Science Institute
M. S. Kondria
Південноукраїнський національний педагогічний університет імені К. Д. Ушинського

Abstract

The evolution of the microstructure of tungsten under electron irradiation and postirradiation annealing has been modelled using a multiscale approach based on Cluster Dynamics simulations. In these simulations, both self-interstitials atoms (SIA) and vacancies, carbon atoms isolated or in clusters, are considered. Isochronal annealing has been simulated in pure tungsten and tungsten with carbon, focusing on recovery stages I and II. The carbon atom, single SIA, single vacancy and vacancy clusters with sizes up to four are treated as the mobile pieces. Their diffusivities as well as the energy formation and binding energies are based on the experimental data and ab initio predictions and some of these parameters have been slightly adjusted, without modifying the interaction character, on isochronal annealing experimental data. The recovery peaks are globally well reproduced. These simulations allow interpreting the second recovery peak as the effect of carbon.

Article Details

Issue
No. 1 (2017)
Section
Materials Physics
Author Biographies

A. R. Gokhman, Південноукраїнський національний педагогічний університет імені К. Д. Ушинського

завідувач кафедри фізики

M. S. Kondria, Південноукраїнський національний педагогічний університет імені К. Д. Ушинського

аспірант

References

Gokhman A., Pecko S. and Slugeň V. (2015). Simulation of nanostructure evolution under helium implantation in Fe-(2.5-12.5)at% Cr alloys at temperature of 343K. Radiation Effects and Defects in Solids: Incorporating Plasma Science and Plasma Technology. Vol. 170 –P . 745-757.

Fu C. C., Dalla Torre, Willaime F., Bocquet J.L., Barbu A.. (2005). Multiscale modelling of defect kinetics in irradiated iron. Nature Materials Vol. 4 – P. 68-74.

Fikar J., Schaublin R.. (2009). Nucl. Instr. Methods Phys. Res Vol. B 267. – P. 3218–3222.

Dieter G. E. (1988). Mechanical Metallurgy. – London, symmetric edition. : McGraw-Hill Book Company (in England)

Li Y. G., Zhou W. H., Ning R. H., Huang L. F., Zeng Z., Ju X. (2012). Cluster Dynamics Model for Accumulation of Helium in Tungsten under Helium Ions and Neutron Irradiation. Commun. Comput. Phys. Vol. 11. – P. 1547-1568

Satta A., Willaime F., Stefano de Gironcoli. (1998). Vacancy self-diffusion рarameters in tungsten: Finite electron-temperature LDA calculations. Phys. Rev. Vol. B 57 – P. 11184.

Derlet P. M., Nguyen-Manh D., Dudarev S. L., (2007). Multiscale modeling of crowdion and vacancy defects in body-centered-cubic transition metals. Phys. Rev. Vol. B 76. – P. 054107

Withop Arthur (1966). ). The diffusion of carbon into tungsten (PhD Thesis, The University of Arizona, the United States).

Aleksandrov L. N. (1960). Zavodskaya Laboratorya. Vol. 25. P. 925-935.

Becker, J. A., E. I. Becker, and Re. G. Brandes. (1961). J. Appl. Phys. Vol. 32. – P. 411-423.

Bushmer C. P., Crayton P. H. (1971). Carbon Self-Diffusion in Tungsten Carbide. Journal of Material Science No 6 – P. 981-988.

Yue-Lin Liu, Hong-Bo Zhou, Shuo Jin, Ying Zhang, Guang-Hong Lu. (2010). Dissolution and diffusion properties of carbon in tungsten. J. Phys. Vol. 22 – P. 445504 (6pp).

Tyson W. R, Miller W. A. (1977). Surface free energies of solid metals: Estimation from liquid surface tension measurements. Surface Science. Vol. 62 – P. 67-276.

Becquart C. S., C. Domain, U. Sarkar, and et al. (2010). J. Nucl. Mater. Vol. 403 – P. 75 -88.

Nguyen-Manh D. (2009). Modelling of Point Defect-Impurity Interaction in Tungsten and other Bcc Transition Metals. Advanced Materials Research No 59 – P. 253-256.

LSODA is part of the ODEPACK provided by Alan C. Hindmarsh 1984 onthe CASC server of the Lawrence Livermore National Laboratory, Livermore, CA 94551, USA.

Gear C.W. (1971). Numerical Initial Value Problems in Ordinary Differential Equations. Gear– NJ. : Prentice-Hall,Englewood Cliffs. (in USA)

Neely H., Keeper D. W., Sosin A. (1968). Keeper and A. Sosin, Electron Irradiation and Recovery of Tungsten. Phys. stat. sol. Vol. 28. – P. 675-682.

Ngayam-Happy R., Olsson P., Becquart C. S., Domain C. (2010). Isochronal annealing of electron-irradiated dilute Fe alloys modelled by an ab initio based AKMC method: Influence of solute–interstitial cluster properties. Journal of Nuclear Materials.

Vol. 407. – P. 16–28