The influence of carbon impurities on the formation of loops in tungsten irradiated with self-ions

被引:25
作者
Castin, N. [1 ]
Dubinko, A. [1 ]
Bonny, G. [1 ]
Bakaev, A. [1 ]
Likonen, J. [2 ]
De Backer, A. [3 ]
Sand, A. E. [4 ]
Heinola, K. [4 ]
Terentyev, D. [1 ]
机构
[1] Nucl Mat Sci Inst, Ctr Etud Energie Nucl SCK CEN, Studie Ctr Kerneenergie Ctr, Boeretang 200, B-2400 Mol, Belgium
[2] VTT Tech Res Ctr Finland, POB 1000, FIN-02044 Espoo, Finland
[3] Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England
[4] Univ Helsinki, Dept Phys, POB 43, FI-00014 Helsinki, Finland
关键词
NEUTRON-IRRADIATION; RADIATION-DAMAGE; SIMULATION; RECOVERY; MICROSTRUCTURE; CASCADES; IMPACT;
D O I
10.1016/j.jnucmat.2019.151808
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The microstructure changes taking place in W under irradiation are governed by many factors, amongst which C impurities and their interactions with self-interstitial atoms (SIA). In this work, we specifically study this effect by conducting a dedicated 2-MeV self-ions irradiation experiment, at room temperature. Samples were irradiated up to 0.02, 0.15 and 1.2 dpa. Transmission electron microscopy (TEM) expectedly revealed a large density of SIA loops at all these doses. Surprisingly, however, the loop number density increased in a non-monotonous manner with the received dose. Performing chemical analysis with secondary ion spectroscopy measurements (SIMS), we find that our samples were likely contaminated by C injection during the irradiation. Employing an object kinetic Monte Carlo (OKMC) model for microstructure evolution, we demonstrate that the C injection is the likely factor explaining the evolution of loops number density. Our findings highlight the importance of the well-known issue of C injection during ion irradiation experiments, and demonstrate how OKMC models can help to rationalize this effect. (C) 2019 The Authors. Published by Elsevier B.V. All rights reserved.
引用
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页数:8
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