Irradiation effects in tungsten-From surface effects to bulk mechanical properties

被引:17
作者
Riesch, J. [1 ]
Feichtmayer, A. [1 ,2 ]
Coenen, J. W. [3 ,4 ]
Curzadd, B. [1 ]
Gietl, H. [5 ]
Hoeschen, T. [1 ]
Manhard, A. [1 ]
Schwarz-Selinger, T. [1 ]
Neu, R. [1 ,2 ]
机构
[1] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
[2] Tech Univ Munich, D-85748 Garching, Germany
[3] Forschungszentrum Julich, Inst Energie & Klimaforsch Plasmaphys, D-52425 Julich, Germany
[4] Univ Wisconsin, Dept Engn Phys, Madison, WI 53706 USA
[5] Oak Ridge Natl Lab, Mat Sci & Technol Div, Oak Ridge, TN 37831 USA
关键词
Tungsten; Wire; Ion irradiation; Tensile test; Embrittlement; Ductility; MICROSTRUCTURE; FRACTURE; DAMAGE; DEFORMATION; TEMPERATURE; DEUTERIUM; BEHAVIOR; FISSION; PURE;
D O I
10.1016/j.nme.2021.101093
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Advanced materials such as tungsten fibre-reinforced composites allow to overcome severe weaknesses of the baseline materials for plasma-facing components - copper and tungsten. The effect of the fusion environment on the mechanical properties of these materials, e.g. the embrittlement by neutron irradiation, plays a key role for the development of future fusion reactors. To simulate this effect, high-energy ions are used as a substitute for the displacement damage by neutrons. We propose the use of very fine tungsten wire as a possibility of studying the influence of irradiation damage on the mechanical properties. This is possible as they allow full-depth irradiation of almost the entire volume despite the limited penetration depth of ions. Geometrical size effects are mitigated due to the nanoscale microstructure of the wire. In addition, similar wire is used in tungsten fibre-reinforced composites. Thus, the investigation of irradiated wire can directly be used for the prediction of the bulk composite properties. For the proof of this concept tungsten wire with a diameter of 16 mu m was electrochemically thinned to 5 mu m and irradiated with 20.5 MeV W6+ ions. The mechanical properties were subsequently determined by macroscopic tensile testing. Irradiation to 0.3, 1 and 9 dpa did not lead to a change of the mechanical behaviour. Both strength and ductility, the latter indicated by the reduction of area, were similar to the as-fabricated state.
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页数:8
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