Thermal annealing behavior of hydrogen and surface topography of H2+ ion implanted tungsten

被引:5
|
作者
Zhang, Jiandong [1 ,2 ]
Jiang, Weilin [2 ]
Zhu, Zihua [2 ]
Shao, Lin [3 ]
Price, Lloyd [3 ]
Zhao, Jiangtao [1 ]
Wang, Tieshan [1 ]
机构
[1] Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou, Gansu, Peoples R China
[2] Pacific Northwest Natl Lab, Richland, WA USA
[3] Texas A&M Univ, Dept Nucl Engn, College Stn, TX 77843 USA
基金
中国国家自然科学基金;
关键词
Hydrogen release; hydrogen blister; tungsten; ToF-SIMS; DEUTERIUM RETENTION; DAMAGED TUNGSTEN; LOW-ENERGY; RELEASE;
D O I
10.1080/00223131.2018.1428126
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Tungsten (W) has been proposed as a plasma-facing material in fusion reactors due to its outstanding properties. Degradation of the material properties is expected to occur as a result of hydrogen (H) isotope permeation and trapping in W. In this study, two polycrystalline W plates were implanted with 80 keV H-2(+) ions to a fluence of 2x 10(21) H+/m(2) at room temperature (RT). Time-of-flight secondary ion mass spectrometry (ToF-SIMS), focused ion beam (FIB), and scanning electron microscopy (SEM) were used for sample characterization. The SIMS data shows that H atoms are distributed well beyond the ion projected range. Isochronal annealing appears to suggest two H release stages that might be associated with the reported activation energies. H release at RT was observed between days 10 and 70 following ion implantation, and the level was maintained over the next 60days. In addition, FIB/SEM results exhibit H-2 blister formation near the surface of the as-implanted W. The blister distribution remains unchanged after thermal annealing up to 600 C.
引用
收藏
页码:703 / 708
页数:6
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