Dynamic interaction between the dislocations and cavities in tungsten during tensile test
Dynamic interaction between the dislocations and cavities in tungsten during tensile test
复制标题
DOI：
10.1016/j.nme.2022.101130
复制
发表时间：
2022-02
影响因子：
2.6
通讯作者：
Kouichi Tougou;Maoto Fukui;K. Fukumoto;R. Ishigami;K. Yabuuchi
中科院分区：
文献类型：
--
作者：
Kouichi Tougou;Maoto Fukui;K. Fukumoto;R. Ishigami;K. Yabuuchi
通过拉伸试验中的TEM原位观察，研究了核聚变反应堆偏滤器候选材料钨中空腔（氦泡）的辐照硬化因子。根据线张力模型，利用位错的脱出行为计算了障碍势垒强度α。在W中测得直径为2nm的空腔的障碍势垒强度α为0.53 ± 0.02。由于螺型位错与空洞之间的动态相互作用，除障碍物切割机制外，交叉滑移行为的比例约为11%。与其它BCC结构材料相比，W中螺位错的交滑移行为所占比例较小。
The irradiation hardening factor of the cavities (helium bubbles) in tungsten, as the divertor candidate material, in nuclear fusion reactor, has been investigated through anin-situTEM observation during tensile test. The obstacle barrier strength α has been calculated by the bow-out behavior of a dislocation based on the line tension model. The obstacle barrier strength α of the cavity with a diameter of 2 nm in W has been measured to be 0.53 ± 0.02. The fraction of cross-slip behavior except the obstacle-cutting mechanism owing to the dynamic interaction between a dislocation of screw type and a cavity has been about 11 %. The fraction of cross-slip behavior of the screw dislocation in W has been smaller than those of other BCC structure materials.