Maximum implementation capacity of fusion power reactors

被引:6
作者
Asaoka, Y [1 ]
Okano, K
Yoshida, T
Hiwatari, R
Tokimatsu, K
机构
[1] CRIEPI, Tokyo 2018511, Japan
[2] RITE, Res Inst Innovat Technol Earth, Minato Ku, Tokyo 1050003, Japan
来源
FUSION TECHNOLOGY | 2001年 / 39卷 / 02期
关键词
D O I
10.13182/FST01-A11963288
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
Maximum implementation capacity of commercial fusion reactors based on breeding and supply of tritium has been investigated. The implementation capacity of fusion power reactors depends upon the net tritium breeding gain and a requirement of the initial supply of tritium for a steady commercial operation. In the reference case, the maximum implementation capacity is 7 GWe in 10 years after the year of fusion introduction, 118 GWe in 20 years and 488 GWe in 25 years. It is mainly limited by the industrial construction capacity after 25 years. The maximum implementation capacity is largely depends on the preparation interval of operation as well as the tritium breeding performance. It means that subsequent reactors must start operation as soon as possible not to leave produced tritium. The requirement to the tritium breeding for a satisfactory implementation effusion power plants is also discussed. In the case that fusion implementation is similar to the increase of fission reactors in last 40 years, tritium breeding ratio of 1.08 will be required for the early plants. On the other hand, tritium breeding ratio of 1.02 is sufficient when fusion plants are widely deployed.
引用
收藏
页码:518 / 522
页数:5
相关论文
共 4 条
[1]   DEUTERIUM-TRITIUM FUEL SELF-SUFFICIENCY IN FUSION-REACTORS [J].
ABDOU, MA ;
VOLD, EL ;
GUNG, CY ;
YOUSSEF, MZ ;
SHIN, K .
FUSION TECHNOLOGY, 1986, 9 (02) :250-285
[2]   Requirements of tritium breeding ratio for early fusion power reactors [J].
Asaoka, Y ;
Okano, K ;
Yoshida, T ;
Tomabechi, K .
FUSION TECHNOLOGY, 1996, 30 (03) :853-863
[3]  
Asaoka Y., 2000, 18 IAEA FUS EN C SOR
[4]  
KONISHI S, 2000, IN PRESS J PLASMA FU