In future fusion reactors, plasma-facing materials (PFMs) have to withstand unique conditions such as high temperatures, ion and neutron irradiation. Tungsten (W) has been established as main candidate material due to its favorable properties regarding the fusion environment but brings one major challenge: Its brittleness at moderate temperatures can lead to failure of tungsten components. Tungsten fiber-reinforced tungsten (W_f/W), a tungsten matrix containing drawn tungsten fibers, was developed to mitigate this problem by using extrinsic toughening mechanisms to achieve pseudo-ductility. The deuterium (D) retention in W_f/W manufactured by chemical vapor deposition (CVD) has been investigated using W_f/W single layered model systems consisting of a single plane of unidirectional tungsten fibers embedded in a tungsten matrix produced by CVD. Various parameters with potential influence on the D retention, such as the choice of an erbium oxide interface and potassium doping, have been included in the investigation. The samples have been ground to varying distances between surface and fiber plane - exposing distinct details of the W_f/W microstructures at the surface. The samples were exposed to a low temperature D plasma at 370 K for 72 h resulting in a total fluence of 10²⁵ D/m². The D retention of all samples was measured by nuclear reaction analysis (NRA) and thermal desorption spectroscopy (TDS). The D retention in W_f/W composites is higher than in reference samples made from hot-rolled W by factors between 2 and 5. In addition, a comparison of NRA and TDS data indicates that D penetrates faster into the depth of W_f/W material than into hot-rolled tungsten.

在未来的聚变反应堆中，面向等离子体的材料（PFM）必须承受独特的条件，例如高温，离子和中子辐照。钨（W）由于其在熔融环境方面的优越性能而被确立为主要候选材料，但带来了一个重大挑战：在中等温度下的脆性可能导致钨组件的失效。钨纤维增强钨（W _f / W）是一种含有拉丝钨纤维的钨基体，旨在通过使用外在增韧机制来实现假延展性来缓解此问题。使用W _f研究了通过化学气相沉积（CVD）制造的W _f / W中的氘（D）保留量/ W单层模型系统，该系统包含嵌入CVD生产的钨基体中的单面单向钨纤维平面。对D保留有潜在影响的各种参数，例如氧化oxide界面的选择和钾的掺杂，已包括在研究中。将样品研磨至表面和纤维平面之间的不同距离-在表面上暴露出W _f / W微结构的不同细节。将样品暴露于370 K的低温D等离子体中72 h，总通量为10 ²⁵ D / m ²。通过核反应分析（NRA）和热脱附光谱（TDS）测量所有样品的D保留率。W _f中的D保留/ W复合材料比由热轧W制造的参考样品高2到5倍。此外，对NRA和TDS数据的比较表明，D渗透到W _f / W材料的深度比渗透到W- / W材料的深度要快。轧制钨。