Status and prospect of JT-60 plasma control and diagnostic data processing systems for advanced operation scenarios

被引：13

作者：

Kurihara, K. ^{[1
]}

Yonekawa, I. ^{[1
]}

Kawamata, Y. ^{[1
]}

Sueoka, M. ^{[1
]}

Hosoyama, H. ^{[1
]}

Sakata, S. ^{[1
]}

Ohshima, T. ^{[1
]}

Sato, M. ^{[1
]}

Kiyono, K. ^{[1
]}

Ozeki, T. ^{[1
]}

机构：

[1] Japan Atom Energy Agcy, Naka, Ibaraki 3110193, Japan

来源：

FUSION ENGINEERING AND DESIGN | 2006年 / 81卷 / 15-17期

关键词：

tokamak; plasma real-time control; diagnostic data processing; advanced operation scenario; JT-60; ITER;

D O I：

10.1016/j.fusengdes.2006.04.058

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：

The large tokamak fusion device JT-60 is expected to explore more advanced tokamak discharge scenarios toward the ITER and a future power reactor. Since various experimental issues are to be adequately discussed, and possibly to be solved in JT-60, the plasma real-time control system has been drastically improved with remodelling in hardware as well as in software. To satisfy the requirements, a "multiple networks" structure is employed as a basic principle of the remodelling. Distributed processors for diagnostics, actuators, and supervisory controllers are linked through a reflective memory (RM) network for fast, real-time communication. Similarly, advanced and complex calculations to reproduce plasma shape and profiles are performed by several processors connected to the same RM network. In this report, we discuss the developments to improve the JT-60 plasma control and data processing systems. In addition, a future plasma control system leading to a standard design for a power reactor is outlined, which is based on the 20-year plasma operation experience. (c) 2006 Elsevier B.V. All rights reserved.

引用

页码：1729 / 1734

页数：6

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