Circuit analyses of the filament ion source power supplies for the ITER neutral beam test facility

被引:0
作者
Bigi, M. [1 ,2 ]
Zanotto, L. [1 ]
机构
[1] EURATOM, ENEA, Consorzio RFX, Corso Stati Uniti 4, I-35127 Padua, Italy
[2] Univ Cagliari, DIEE, I-09123 Cagliari, Italy
来源
21ST IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING - SOFE 05 | 2006年
关键词
D O I
暂无
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
This paper describes circuit simulations of the filament heating circuit for the neutral beam test facility of the International Thermonuclear Experimental Reactor (ITER). The novel features of ITER filament heating circuit are studied both in normal operation and under fault conditions. The proposed scheme is found capable of performing as required and results are illustrated useful for further detailing of the design.
引用
收藏
页码:413 / 416
页数:4
相关论文
共 15 条
[11]  
MONDINO PL, 2000, NUCL FUS, V40
[12]  
ONALI R, 2005, DISCHARGE FILAMENT P
[13]  
ROMBAULT C, 1987, POWER ELECT CONVERTE, V2
[14]  
Roth J. R., 1995, IND PLASMA ENG, V1, DOI DOI 10.1201/9781420050868
[15]  
ZHENG T, 2003, IEEE T POWER DELIVER, V18, P2