HYDROGEN TRANSPORT AND SOLUBILITY IN 316L AND 1.4914 STEELS FOR FUSION-REACTOR APPLICATIONS

被引：130

作者：

FORCEY, KS ^{[1
]}

ROSS, DK ^{[1
]}

SIMPSON, JCB ^{[1
]}

EVANS, DS ^{[1
]}

机构：

[1] MAX PLANCK INST PLASMA PHYS,NET TEAM,D-8046 GARCHING,FED REP GER

来源：

JOURNAL OF NUCLEAR MATERIALS | 1988年 / 160卷 / 2-3期

关键词：

The above work was financed by the Commission of the European Communities as part of the European Fusion Project. The authors would like to express their gratitude to D.R. Harries who initiated the present research programme into tritium permeation barriers for NET;

D O I：

10.1016/0022-3115(88)90038-4

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

引用

页码：117 / 124

页数：8