TRITIUM IN FUSION POWER-REACTOR BLANKETS

被引：2
|
作者：
HICKMAN, RG [1 ]
机构：
[1] UNIV CALIF,LAWRENCE LIVERMORE LAB,LIVERMORE,CA 94550
来源：
NUCLEAR TECHNOLOGY | 1974年 / 21卷 / 01期
关键词：
NUCLEAR FUELS - Analysis - TRITIUM;
D O I：
10.13182/NT74-A31378
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：
Several related problems involving the recovery of tritium from the breeding blanket in fusion power reactors are considered. They include the use of stagnant lithium blankets, the use of lithium as a regenerable getter pump, and the use of breeder materials that are lithium intermetallic alloys. Transient tritium recovery rates during startup are also estimated.
引用
收藏
页码：39 / 49
页数：11
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