FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Quench protection of the poloidal field superconducting coil system for the EAST tokamak

P. Fu, Z.Q. Song, G. Gao, L.J. Tang, Y.B. Wu, L.S. Wang, X.Y. Liang2006年被引用 52Nuclear FusionIF 3出版社

This paper gives a description of the poloidal field coil quench protection (QP) and control of the EAST poloidal field power supplies. A configuration of the QP hardware and an operating scenario are presented; the QP design principle in the EAST tokamak is also introduced.

日本語訳

本論文は、EASTのポロイダル磁場コイルのクエンチ保護(QP)およびポロイダル磁場電源の制御について述べるものである。QPハードウェアの構成と運転シナリオを示し、EASTトカマクにおけるQP設計原理についても紹介する。

装置

east高精度(タイトル一致)

wiki

EAST
この論文にはまだAI要約がありません。

関連論文

Upgrade of poloidal field coils current measurement system on Experimental Advanced Superconducting Tokamak

2019Fusion Engineering and Design

Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak

2019Fusion Engineering and Design

Analysis of an unmitigated quench in a poloidal field coil of ITER

2003Fusion Engineering and Design

Multi-coupled commutation analysis in EAST poloidal field quench protection circuits based on fuse model

2020Fusion Engineering and Design

Implementation and design of the control system for poloidal field power supply

2020Fusion Engineering and Design

Bayesian optimization of poloidal field coil positions in tokamaksOpen Access

2025Physics of Plasmas

Magnetic configuration of a poloidal divertor tokamak

1980Nuclear Fusion

The design of quench protection of EAST toroidal field power supply system

2006Fusion Engineering and Design

Poloidal magnetic field around a tokamak magnetic surface

1998Physics of Plasmas

Innovative application of a magnet system to fusion power

1998Fusion Engineering and Design