Hydrogen behavior in damaged tungsten by high-energy ion irradiation

被引：32

作者：

Fukumoto, M. ^{[1
]}

Kashiwagi, H. ^{[1
]}

Ohtsuka, Y. ^{[1
]}

Ueda, Y. ^{[1
]}

Nobuta, Y. ^{[2
]}

Yagyu, J. ^{[3
]}

Arai, T. ^{[3
]}

Taniguchi, M. ^{[3
]}

Inoue, T. ^{[3
]}

Sakamoto, K. ^{[3
]}

机构：

[1] Osaka Univ, Grad Sch Engn, Osaka 5650871, Japan

[2] Hokkaido Univ, Lab Plasma Phys & Engn, Kita Ku, Sapporo, Hokkaido 0608628, Japan

[3] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan

来源：

JOURNAL OF NUCLEAR MATERIALS | 2009年 / 386-88卷

关键词：

RESEARCH-AND-DEVELOPMENT; DEUTERIUM RETENTION; BLISTER FORMATION; COMPONENTS; VESSEL; ITER;

D O I：

10.1016/j.jnucmat.2008.12.213

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Effects of radiation damage on the behavior of hydrogen trapped in tungsten were investigated using a mixed hydrogen-carbon ion beam and deuterium ion beam. Radiation damage was produced by 300 and 700 keV negative hydrogen ion beams. The number density of blisters formed on the radiation-damaged samples was less than an undamaged sample. SIMS measurements showed that post-implanted deuterium was mainly trapped at radiation damage sites. These results suggest that hydrogen accumulation at the grain boundaries is greatly decreased due to significant trapping of hydrogen isotopes at radiation damage sites. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：768 / 771

页数：4

共 15 条

[1] Retention of ion-implanted deuterium in tungsten pre-irradiated with carbon ions [J].