TRITIUM AGING OF ZIRCONIUM COBALT

被引：14

作者：

HEICS, AG

SHMAYDA, WT

机构：

来源：

FUSION TECHNOLOGY | 1992年 / 21卷 / 02期

关键词：

D O I：

10.13182/FST92-A29887

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：

Zirconium cobalt (ZrCo) is being evaluated as an alternative to uranium for tritium storage. The pumping speed and pressure-composition-temperature isotherm profiles for the ZrCo hydrogen and tritium systems were measured to determine isotopic differences and the effect of He-3 induced aging on ZrCo performance. Hydrogen is pumped by ZrCo at a slightly faster rate than tritium under identical test conditions. The ZrCo/H-2 system has a slightly lower equilibrium pressure compared to the ZrCo/T2 system at corresponding compositions. Aging ZrCo with tritium for 57 days appears to have no noticeable effect on the tritium pumping speed relative to virgin ZrCo.

引用

页码：1030 / 1034

页数：5

共 11 条

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