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

页码：1624 / 1627

页数：4

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