当前位置: X-MOL 学术J. Nucl. Mater. › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
Spark Plasma Sintered Tungsten – Mechanical Properties, Irradiation Effects and Thermal Shock Performance
Journal of Nuclear Materials ( IF 2.8 ) Pub Date : 2020-09-11 , DOI: 10.1016/j.jnucmat.2020.152518
Jiří Matějíček , Jakub Veverka , Chao Yin , Monika Vilémová , Dmitry Terentyev , Marius Wirtz , Mauricio Gago , Andrii Dubinko , Hynek Hadraba

Tungsten-based materials are the most prospective candidates for the plasma facing components for future fusion devices, such as DEMO. In order to improve their properties, various modifications are being developed, including composites, alloys, and different processing routes. Spark plasma sintering (SPS) is among the prospective preparation technologies; thanks to the relatively low temperatures and short processing times, it enables the preservation of fine grain structure, beneficial for radiation resistance. In a previous study, SPS W has shown promising mechanical properties at moderate temperatures, however, the irradiation effects were yet to be investigated.

Fine-grained W was prepared by spark plasma sintering. Together with other W-based materials, the samples were neutron-irradiated at the BR2 reactor at 600 and 1000°C up to 0.24 and 0.7 dpa, respectively. Mechanical testing - including tensile test and fracture toughness tests - was performed in irradiated and un-irradiated states in the 200-600°C temperature range. Fractographic observations were performed to help in understanding the impact of the irradiation effects on the fracture mechanism. For the SPS W, a shift of DBTT from ∼300°C to ∼600°C due to irradiation was observed. High heat flux testing was carried out in repeated thermal shock mode at the PSI-2 device at room temperature, 400 and 1000°C and fluxes up to 1.6 GW/m2. The results showed rather promising resistance to cracking under these conditions. In these tests, the SPS tungsten showed comparable or better performance than reference, ITER-qualified tungsten material.



中文翻译:

放电等离子烧结钨–力学性能,辐照效应和热冲击性能

钨基材料是面向未来聚变设备(如DEMO)的面向等离子体部件的最有希望的候选材料。为了改善其性能,正在开发各种修改形式,包括复合材料,合金和不同的加工路线。火花等离子体烧结(SPS)是预期的制备技术之一。由于相对较低的温度和较短的处理时间,因此可以保留细小晶粒结构,有利于抗辐射。在以前的研究中,SPS W在中等温度下显示出令人鼓舞的机械性能,但是,辐射效果尚待研究。

通过火花等离子体烧结制备细粒W。将样品与其他基于W的材料一起在BR2反应器中分别于600和1000°C分别进行中子辐照,分别达到0.24和0.7 dpa。机械试验-包括拉伸试验和断裂韧性试验-在200-600°C的温度范围内以辐照和未辐照状态进行。进行了分形观察,以帮助理解辐射作用对断裂机理的影响。对于SPS W,观察到由于辐照,DBTT从〜300°C移至〜600°C。在室温,400和1000°C下,在PSI-2设备上以重复热冲击模式进行了高热通量测试,通量高达1.6 GW / m 2。结果表明在这些条件下抗裂性相当有希望。在这些测试中,SPS钨表现出与ITER认证的参考钨材料相当或更好的性能。

更新日期:2020-09-11
down
wechat
bug