Deuterium retention on He-irradiated F82H with surface impurity layer

被引：5
|
作者：
Shinoda, N. [1 ]
Yamauchi, Y. [1 ]
Nobuta, Y. [1 ]
机构：
[1] Hokkaido Univ, Lab Plasma Phys & Engn, Kita Ku, Sapporo, Hokkaido 0608628, Japan
来源：
JOURNAL OF NUCLEAR MATERIALS | 2015年 / 463卷
关键词：
FERRITIC STEEL; DESORPTION BEHAVIOR; STAINLESS-STEEL; DAMAGE; WATER;
D O I：
10.1016/j.jnucmat.2015.01.037
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The deuterium retention/desorption behavior of F82H has been studied to clarify the effect of radiation damage with respect to the impurity layer. To evaluate the effects of oxygen impurities, non-oxidized and thermally oxidized samples were prepared with the introduction of radiation damage through He irradiation. The amount of deuterium retained in the thermally oxidized samples was less than that of the non-oxidized samples. The amount of deuterium retained in the oxidized sample increased after He irradiation. The retention/desorption behaviors were discussed in the surface chemical state. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码：1001 / 1004
页数：4
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