Overview of Instrumentation and Control in the Neutral Beam Test Facility

被引：0

作者：

Luchetta, A. ^{[1
]}

Manduchi, G. ^{[1
]}

Taliercio, C. ^{[1
]}

Rigoni, A. ^{[1
]}

Pomaro, N. ^{[1
]}

Moressa, M. ^{[1
]}

Dal Bello, S. ^{[1
]}

Grando, L. ^{[1
]}

Battistella, M. ^{[1
]}

Paolucci, F. ^{[2
]}

Labate, C. ^{[2
]}

机构：

[1] Consorzio RFX, Padua, Italy

[2] Fus Energy, Barcelona, Spain

来源：

2017 EUROPEAN CONFERENCE ON CIRCUIT THEORY AND DESIGN (ECCTD) | 2017年

关键词：

ITER; additional heating; heating neutral beam injector; neutral beam test facility; instrumentation and control; ITER;

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：

The ITER Project is an international collaboration based in southern France to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The heating neutral beam injectors (HNB) are ITER additional heating systems that are needed to achieve the ITER plasma high-confinement regime. The Neutral Beam Test Facility (NBTF) is an R&D program established by ITER. Its purpose is to provide a true reliable HNB for ITER, able to achieve full performance (16.5 MW, 3600 s beam-on time). Two experiments are foreseen in the NBTF, namely SPIDER, the ITER full-size ion source, and MITICA the full prototype of the ITER HNB. The paper will describe the NBTF focusing on the instrumentation and control of the SPIDER and MITICA experiments.

引用

页数：4

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