Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

被引：8
|
作者：
Kobayashi, Makoto [1 ]
Shimada, Masashi [2 ]
Taylor, Chase N. [2 ]
Buchenauer, Dean [3 ]
Kolasinski, Robert [3 ]
Koyanagi, Takaaki [4 ]
Nobuta, Yuji [5 ]
Hatano, Yuji [6 ]
Oya, Yasuhisa [7 ]
机构：
[1] Natl Inst Fus Sci, Natl Inst Nat Sci, 322-6 Oroshi, Toki, Gifu 5095202, Japan
[2] Idaho Natl Lab, Idaho Falls, ID USA
[3] Sandia Natl Labs, Albuquerque, NM USA
[4] Oak Ridge Natl Lab, Oak Ridge, TN USA
[5] Hokkaido Univ, Sapporo, Hokkaido, Japan
[6] Univ Toyama, Hydrogen Isotope Res Ctr, Toyama, Japan
[7] Shizuoka Univ, Shizuoka, Japan
来源：
FUSION ENGINEERING AND DESIGN | 2019年 / 146卷
关键词：
Tungsten; Neutron; Divertor; TDS; INDUCED DAMAGE; HYDROGEN; ENERGY;
D O I：
10.1016/j.fusengdes.2019.03.003
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) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.
引用
收藏
页码：1624 / 1627
页数：4
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