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

Irradiation effects in tungsten—From surface effects to bulk mechanical properties
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钨的辐照效应——从表面效应到整体机械性能

DOI:
10.1016/j.nme.2021.101093
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发表时间:
2021
影响因子:
2.6
通讯作者:
R. Neu
R. Neu
中科院分区:
物理与天体物理2区
文献类型:
--
作者:
Johann Riesch;J. Coenen;B. Curzadd;A. Feichtmayer;L. Garrison;T. Höschen;A. Kärcher;A. Manhard;T. Schwarz;A. Müller;B. Wielunska;R. Neu

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钨纤维增强复合材料等先进材料可以克服面向等离子体组件的基础材料(铜和钨)的严重弱点。聚变环境对这些材料机械性能的影响,例如中子辐照引起的脆化,对于未来聚变反应堆的发展起着关键作用。为了模拟这种效应,使用高能离子来代替中子造成的位移损伤。我们建议使用非常细的钨丝作为研究辐照损伤对机械性能影响的可能性。这是可能的,因为尽管离子的穿透深度有限,但它们允许几乎整个体积的全深度照射。由于线材的纳米级微观结构,几何尺寸效应得到了缓解。此外,类似的丝也用于钨纤维增强复合材料中。因此,辐照线的研究可以直接用于预测块状复合材料的性能。为了证明这一概念,将直径为 16 μm 的钨丝通过电化学方法细化至 5 μm,并用 20.5 MeV W 6+ 离子进行辐照。随后通过宏观拉伸测试确定机械性能。 0.3、1 和 9 dpa 的辐照不会导致机械行为的变化。强度和延展性(后者通过面积减少来表示)与制造状态相似。
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, eg 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 μ m was electrochemically thinned to 5 μ m and irradiated with 20.5 MeV W 6+ 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.
DOI: 10.1016/j.jnucmat.2015.01.053
发表时间: 2015-07-01
影响因子: 3.1
作者:
Armstrong, D. E. J.;Hardie, C. D.;Roberts, S. G.
通讯作者: Roberts, S. G.