Tritium permeation behavior through pyrolytic carbon in tritium production using high-temperature gas-cooled reactor for fusion reactors

被引:2
|
作者
Ushida, H. [1 ]
Katayama, K. [1 ]
Matsuura, H. [2 ]
Yamamoto, R. [1 ]
Fukada, S. [1 ]
Goto, M. [3 ]
Nakagawa, S. [3 ]
机构
[1] Kyushu Univ, Dept Adv Energy Engn Sci, Kasuga, Fukuoka, Japan
[2] Kyushu Univ, Dept Appl Quantum Phys & Nucl Engn, Fukuoka, Japan
[3] Japan Atom Energy Agcy, Oarai, Ibaraki, Japan
来源
NUCLEAR MATERIALS AND ENERGY | 2016年 / 9卷
关键词
Pyrolytic carbon; Hydrogen permeation; Tritium permeation barrier;
D O I
10.1016/j.nme.2016.09.004
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
Under tritium production method using a high-temperature gas-cooled reactor loaded Li compound, Li compound has to be coated by ceramic materials in order to suppress the spreading of tritium to the whole reactor. Pyrolytic carbon (PyC) is a candidate of the coating material because of its high resistance for gas permeation. In this study, hydrogen permeation experiments using a PyC-coated isotropic graphite tube were conducted and hydrogen diffusivity, solubility and permeability were evaluated. Tritium permeation behavior through PyC-coated Li compound particles was simulated by using obtained data. Hydrogen permeation flux through PyC in a steady state is proportional to the hydrogen pressure and is larger than that through Al2O3 which is also candidate coating material. However, total tritium leak within the supposed reactor operation period through the PyC-coated Li compound particles is lower than that through the Al2O3-coated ones because the hydrogen absorption capacity in PyC is considerably larger than that in Al2O3. (C) 2016 Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:524 / 528
页数:5
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