Deuterium diffusion in a chemical densified coating observed by NRA

被引：7
|
作者：
Takagi, I. [1 ]
Kobayashi, T. [1 ]
Ueyama, Y. [1 ]
Moriyama, H. [1 ]
Nakamichi, M. [2 ]
Nakamura, H. [2 ]
Hayashi, K. [2 ]
机构：
[1] Kyoto Univ, Dept Nucl Engn, Sakyo Ku, Kyoto 6068501, Japan
[2] Japan Atom Energy Agcy, Fus Res & Dev Directorate, Ooarai, Ibaraki 3111393, Japan
来源：
JOURNAL OF NUCLEAR MATERIALS | 2009年 / 386-88卷
关键词：
HYDROGEN; PERMEATION; BARRIER; SURFACE; STEEL;
D O I：
10.1016/j.jnucmat.2008.12.275
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Ceramic coatings on structural material are expected as a barrier for tritium permeation in fusion devices. A Cr(2)O(3)-SiO(2)-CrPO(4) coating on stainless steel by use of a chemical densified coating (CDC) method was experimentally studied. The sample disk was exposed to a deuterium plasma and an analyzing beam of (3)He ions irradiated the sample to observe deuterium concentration profiles. It was found that a very long time, typically 10 ks at 563 K, was needed for deuterium to diffuse from the surface to a few pm in depth. The profiles were analyzed with a diffusion model to obtain the diffusion coefficient of deuterium, which was expressed by 1.1 x 10(-10)exp(-0.71 eV/kT) [m(2) s(-1)] between 470 and 723 K. The diffusion coefficient was about 5 orders of magnitude smaller than that in type 304 stainless steel at 563 K. The CDC coating is expected to significantly delay tritium permeation. (c) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码：682 / 684
页数：3
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