Screen test of tritium recovery from stainless steel type 316

被引：6
|
作者：
Perevezentsev, A [1 ]
Watanabe, K
Matsuyama, M
Torikai, Y
机构：
[1] UKAEA, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Toyama Univ, Hydrogen Isotope Res Ctr, Toyama 9308555, Japan
来源：
FUSION SCIENCE AND TECHNOLOGY | 2002年 / 41卷 / 03期
关键词：
D O I：
10.13182/FST41-706
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：
Various techniques, such as wiping, gas-purge at elevated temperatures, heating by flame simultaneously with air-purge, have been tested for decontamination of stainless steel samples exposed to tritium-containing hydrogen at room and elevated temperatures. Effectiveness of the decontamination techniques is compared depending on the history of the sample loading with tritium, treatment after the loading, the sample thickness, etc.
引用
收藏
页码：706 / 710
页数：5
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