作者
Osman El-Atwani, Mert Efe, Bryan Heim, Jean Paul Allain
发表日期
2013/3/1
期刊
Journal of nuclear materials
卷号
434
期号
1-3
页码范围
170-177
出版商
North-Holland
简介
Although tungsten is considered the best candidate as a plasma facing component (PFC) in the divertor region in the International Thermonuclear Experimental Reactor (ITER), severe morphology changes such as cavities, blisters, bubbles and nanostructure formation are expected. Increasing defect sinks in the tungsten microstructure is one of the possible solutions to mitigate the irradiation damage. In this work, helium irradiation at low energy (50 and 200eV) and temperatures of 600 (threshold of vacancy migration) and 950°C were performed on multimodal and ultrafine grained tungsten prepared by spark plasma sintering and severe plastic deformation (SPD), respectively. The multimodal samples consisted of small grains (300–700nm size) juxtaposed to larger grains (1–3μm size). Detachment of the small grains was observed in the multimodal grained tungsten irradiated at 600°C and a fluence of 1×1022m …
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