Bulk hydrogen retention in neutron-irradiated graphite at elevated temperatures

被引:13
|
作者
Atsumi, H. [1 ]
Tanabe, T. [2 ]
Shikama, T. [3 ]
机构
[1] Kinki Univ, Dept Elect & Elect Engn, Higashiosaka, Osaka, Japan
[2] Kyushu Univ, Interdisciplinary Grad Sch Engn Sci, Fukuoka 812, Japan
[3] Tohoku Univ, Inst Mat Res, Sendai, Miyagi 980, Japan
关键词
CARBON MATERIALS; COMPONENTS; ABSORPTION; TRANSPORT; TRITIUM;
D O I
10.1016/j.jnucmat.2009.01.112
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Bulk hydrogen retention and the analysis of absorption kinetics have been studied on graphite samples irradiated with neutrons at various fluences. There are two kinds of hydrogen trapping sites: interstitial cluster loop edge sites (trap 1) and carbon dangling bonds at edge surfaces of a crystallite (trap 2). Neutron irradiation preferably creates trap 2 sites at lower fluences and trap I sites at higher fluences. The dissociation enthalpy becomes 2-3 times higher for neutron-irradiated samples due to the creation of high energy trapping sites. Absorption kinetics, such as diffusion coefficients and absorption rate constants are strongly affected by neutron irradiation and annealing after irradiation. (C) 2009 Elsevier B.V. All rights reserved.
引用
收藏
页码:581 / 584
页数:4
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