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Deuterium distribution and behavior of blisters in pre-damaged and undamaged tungsten
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作者 Cong Li Xiao-Wa Wang +5 位作者 Ran-Ran Su xuan-xin hu Shu-Guang Wei Han-Jun Tu Li-Qun Shi Hong-Liang Zhang 《Tungsten》 EI 2024年第3期647-656,共10页
Tungsten(W),as a plasma-facing material,is subjected to high fluence plasma,resulting in both radiation damage and deuterium(D)retention.This study explores the blistering behavior and D supersaturated layers in both ... Tungsten(W),as a plasma-facing material,is subjected to high fluence plasma,resulting in both radiation damage and deuterium(D)retention.This study explores the blistering behavior and D supersaturated layers in both pre-damaged and undamaged W samples.To achieve a uniform damage profile similar to neutron irradiation,carbon(C)ions with multiple energies and angles were employed.The samples were further irradiated with low-energy D ions under two fluences at temperatures from~380 to 640 K.Using various experimental techniques,we found that pre-damaged W samples can effectively suppress the formation of blistering and lower the threshold temperature at which the surface remains free of blistering.We also observed the prominent D supersaturated peaks within the depth of 20 nm in both pre-damaged and undamaged W.Furthermore,a close correlation between blistering and the D supersaturation was investigated.The results suggest that neutron irradiation in the fusion reactors could increase the critical D concentration for blistering,while a greater depth of damage facilitated the inward diffusion of D,thereby reducing the D concentration gradient and alleviating surface blistering. 展开更多
关键词 Tungsten Deuterium Supersaturated layer Blister Ion irradiation Pre-damage
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