Effect of dual ion beam irradiation (helium and deuterium) on tungsten–tantalum alloys under fusion relevant conditions
Effect of dual ion beam irradiation (helium and deuterium) on tungsten–tantalum alloys under fusion relevant conditions
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DOI：
10.1016/j.nme.2017.02.011
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发表时间：
2017-08
影响因子：
2.6
通讯作者：
S. Gonderman;J. Tripathi;T. J. Novakowski;T. Sizyuk;A. Hassanein
中科院分区：
文献类型：
--
作者：
S. Gonderman;J. Tripathi;T. J. Novakowski;T. Sizyuk;A. Hassanein
选择钨（W）作为ITER中的偏滤器材料是基于其高熔点，低侵蚀和强机械性能。然而，持续的研究表明，W进行严重的形态变化的融合样条件。最近的文献表明，W与其他韧性难熔金属，即钽（Ta）合金化可以解决这些问题中的一些。这些结果为研究W-Ta合金作为ITER和未来DEMO反应堆的面向等离子体组件（PFC）提供了进一步的动力。具体而言，这些合金材料如何响应同时He+和D+离子照射，以及当暴露于融合相关条件时对表面形态的影响。在本研究中，表面形貌的变化进行了研究，在几个W-Ta靶（纯W，W-1%Ta，W-3%Ta，和W-5%Ta）由于同时的He+和D+离子辐照。这项全面的工作可以更深入地了解双离子辐照对W和W-Ta合金表面形貌的协同效应。纯W和W-Ta合金同时被100 eV He+和/或D+离子以不同的混合比例（100%He+，60%D ++40%He+，90%D ++10%He+离子和100%D+离子）辐照，总恒定He通量为6 × 1024 ion m−2，靶温度为1223 K。这项工作表明，材料成分和He/D含量的微小变化对表面形貌演变和性能有显着影响。虽然纯W和W-Ta合金在仅He+辐照下表现出非常受损的表面，但随着D+/He+离子的比率增加，表面形貌演变有明显的抑制。
The selection of tungsten (W) as a divertor material in ITER is based on its high melting point, low erosion, and strong mechanical properties. However, continued investigation has shown W to undergo severe morphology changes in fusion-like conditions. Recent literature suggests alloying W with other ductile refractory metals,viz.tantalum (Ta) may resolve some of these issues. These results provide further motivation for investigating W–Ta alloys as a plasma-facing component (PFC) for ITER and future DEMO reactors. Specifically, how these alloy materials respond to simultaneous He+and D+ion irradiation, and what is the effect on the surface morphology when exposed to fusion relevant conditions. In the present study, the surface morphology changes are investigated in several W–Ta targets (pure W, W-1%Ta, W-3%Ta, and W-5% Ta) due to simultaneous He+and D+ion irradiations. This comprehensive work allows for deeper understanding of the synergistic effects induced by dual ion irradiation on W and W–Ta alloy surface morphology. Pure W and W–Ta alloys were irradiated simultaneously by 100 eV He+and/or D+ions at various mixture ratios (100% He+, 60% D++ 40% He+, 90% D++ 10% He+ions and 100% D+ions), having a total constant He fluence of 6 × 1024ion m−2, and at a target temperature of 1223 K. This work shows that slight changes in materials composition and He/D content have significant impact on surface morphology evolution and performance. While both the pure W and W–Ta alloys exhibit very damaged surfaces under the He+only irradiations, there is a clear suppression of the surface morphology evolution as the ratio of D+/He+ions is increased.