PRELIMINARY CHARACTERIZATION OF ZR9NI11 ALLOY FOR ITS TRITIUM GETTERING PROPERTY IN IN-SITU IRRADIATION TEST

被引：10

作者：

TSUCHIYA, K ^{[1
]}

IMAIZUMI, H ^{[1
]}

KAWAMURA, H ^{[1
]}

OYAMADA, R ^{[1
]}

KABUTOMORI, T ^{[1
]}

WAKISAKA, Y ^{[1
]}

机构：

[1] JAPAN STEEL WORKS LTD,MURORAN,HOKKAIDO 051,JAPAN

来源：

FUSION TECHNOLOGY | 1995年 / 28卷 / 03期

关键词：

D O I：

10.13182/FST95-A30613

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：

An in-situ irradiation test of a fusion blanket is planned in JMTR (Japan Materials Testing Reactor) using lithium containing ceramics as the tritium breeder and beryllium as the neutron multiplier. Therefore, it is necessary to develop getters for the recovery of the tritium gas. In this study, Zr9Ni11 alloy was chosen as a getter, and pressure-composition isotherms between 20 degrees C and 300 degrees C, and other properties were measured for its application. The breakthrough test of hydrogen was carried out with Ar+H-2 gas. The evaluation of the examined getter materials leads to the conclusion that the Zr9Ni11 alloy may be used for the in-situ irradiation test of fusion blanket.

引用

页码：1431 / 1436

页数：6

共 16 条

[1] CHARACTERIZATION OF THE ZRCO-HYDROGEN SYSTEM IN VIEW OF ITS USE FOR TRITIUM STORAGE [J].