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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.
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页码:703 / 708
页数:6
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