Deuterium distribution and behavior of blisters in pre-damaged and undamaged tungsten  

作　　者：Cong Li Xiao-Wa Wang Ran-Ran Su Xuan-Xin Hu Shu-Guang Wei Han-Jun Tu Li-Qun Shi Hong-Liang Zhang 

机构地区：[1]Key Laboratory of Nuclear Physics and Ion-Beam Application,Institute of Modern Physics,Fudan University,Shanghai 200433,China [2]School of Mechanical Engineering,Shanghai Jiao Tong University,Shanghai 200240,China [3]Department of Materials Science and Engineering,University of Wisconsin,Madison WI 53706,USA

出　　处：《Tungsten》2024年第3期647-656,共10页钨科技（英文）

基　　金：supported by the National Key R&D Program of China(Grant No.2017YFA0402503)。

摘　　要：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.

关 键 词：TUNGSTEN DEUTERIUM Supersaturated layer BLISTER Ion irradiation Pre-damage 

分 类 号：TG146.411[一般工业技术—材料科学与工程]