Object kinetic Monte Carlo model for neutron and ion irradiation in tungsten: Impact of transmutation and carbon impurities

被引:38
|
作者
Castin, N. [1 ]
Bonny, G. [1 ]
Bakaev, A. [1 ]
Ortiz, C. J. [2 ]
Sand, A. E. [3 ]
Terentyev, D. [1 ]
机构
[1] Studie Ctr Kerneenergie Ctr Etud Energie Nucl SCK, NMS Unit, Boeretang 200, B-2400 Mol, Belgium
[2] CIEMAT, Lab Nacl Fus Confinamiento Magnet, Ave Complutense 40, E-28040 Madrid, Spain
[3] Univ Helsinki, Dept Phys, POB 43, FI-00014 Helsinki, Finland
关键词
RADIATION-DAMAGE; FUSION ENERGY; PURE TUNGSTEN; ALLOYS; MICROSTRUCTURE; EVOLUTION; MIGRATION; CASCADES; RHENIUM; VACANCY;
D O I
10.1016/j.jnucmat.2017.12.014
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
We upgrade our object kinetic Monte Carlo (OKMC) model, aimed at describing the microstructural evolution in tungsten (W) under neutron and ion irradiation. Two main improvements are proposed based on recently published atomistic data: (a) interstitial carbon impurities, and their interaction with radiation-induced defects (point defect clusters and loops), are more accurately parameterized thanks to ab initio findings; (b) W transmutation to rhenium (Re) upon neutron irradiation, impacting the diffusivity of radiation defects, is included, also relying on recent atomistic data. These essential amendments highly improve the portability of our OKMC model, providing a description for the formation of SIA-type loops under different irradiation conditions. The model is applied to simulate neutron and ion irradiation in pure W samples, in a wide range of fluxes and temperatures. We demonstrate that it performs a realistic prediction of the population of TEM-visible voids and loops, as compared to experimental evidence. The impact of the transmutation of W to Re, and of carbon trapping, is assessed. (C) 2017 SCK.CEN, Belgium. Published by Elsevier B.V. All rights reserved.
引用
收藏
页码:15 / 25
页数:11
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