Optimization of the Poloidal Field Coil System by Using an Integrated Design Code for Tokamak Fusion Reactors

Yuya MIYOSHI; Makoto NAKAMURA; Yuichi OGAWA

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Optimization of the Poloidal Field Coil System by Using an Integrated Design Code for Tokamak Fusion Reactors

机译：托卡马克聚变反应堆集成设计规范对极场场线圈系统的优化

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A platform for an integrated design code has been developed in which the detailed analysis codes for many components of a nuclear fusion reactor are compiled and incorporated into the system analysis code. Here we have introduced the lasma equilibrium code into the integrated design code in order to optimize the poloidal coil system. This makes it possible to evaluate the capability of the flux supply for ramping up the plasma current and the controllability of an elongated plasma owing to vertical stability. We calculated the margin for vertical stability for various positions of a passive conductor.

机译：已经开发了用于集成设计代码的平台，其中将核聚变反应堆许多组件的详细分析代码编译并合并到系统分析代码中。在这里，我们已经将等离子平衡代码引入到集成设计代码中，以优化极向线圈系统。由于垂直稳定性，这使得有可能评估通量供应的用于增加等离子体电流的能力以及细长等离子体的可控制性。我们计算了无源导体各个位置的垂直稳定性裕度。

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《Plasma and Fusion Research》 |2011年第6期|共1页
作者
Yuya MIYOSHI; Makoto NAKAMURA; Yuichi OGAWA;
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中图分类等离子体物理学;
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1. Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak [J] . Xiao B. J., Luo Z. P., Li H., Fusion Engineering and Design . 2019,第Sepa期

机译：EAST托卡马克上可替代偏滤器配置研究的容器内极向场线圈优化设计的进展
2. Design and R&D for the liquid nitrogen cooled poloidal field coil system for the Compact Ignition Tokamak (CIT) [J] . Thome R.J., Pillsbury R.D. Jr. IEEE Transactions on Magnetics . 1988,第2期

机译：紧凑点火托卡马克（CIT）液氮冷却极向场线圈系统的设计和研发
3. The Polo coil, a prototype tokamak poloidal field coil, design features and test results [J] . Darweschsad M., Heller R. IEEE Transactions on Magnetics . 1996,第4期

机译：Polo线圈，托卡马克极向场线圈原型，设计特征和测试结果
4. Poloidal field coil system optimization for the Compact Ignition Tokamak (CIT) [C] . Pillsbury, R.D., Jr., . 1990

机译：紧凑点火托卡马克（CIT）的极向场线圈系统优化
5. SAFETY AND DETERMINISTIC FAILURE ANALYSES IN HIGH-BETA D-D TOKAMAK REACTORS (FUSION SAFETY, ADVANCED FUSION, FUELS-SAFETY). [D] . SELCOW, ELIZABETH CAROL. 1984

机译：高倍率D-D托卡马克反应器的安全性和确定性故障分析（熔断安全，高级熔断，燃料安全）。
6. RF Head Coil Design with Improved RF Magnetic Near-Fields Uniformity for Magnetic Resonance Imaging (MRI) Systems [O] . Sung-Min Sohn, Lance DelaBarre, Anand Gopinath, -1

机译：具有改进的RF电磁近场均匀性的RF头线圈设计用于磁共振成像（MRI）系统
7. Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak [O] . B.J. Xiao, Z.P. Luo, H. Li, 2019

机译：船舶占地面线圈优化设计的进展，以替代脚轮配置研究
8. Integrated-Blanket-Coil (IBC) Concept Applied to the Poloidal Field and Blanket Systems of a Tokamak Reactor [R] . Steiner, D., Block, R. C., Malaviya, B. K. 1983

机译：综合毯 - 线圈（IBC）概念应用于托卡马克反应堆的极向场和橡皮布系统

Optimization of the Poloidal Field Coil System by Using an Integrated Design Code for Tokamak Fusion Reactors

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