Conceptual design of the island divertor coils on the J-TEXT tokamak-Reference-Cited by-同舟云学术

Conceptual design of the island divertor coils on the J-TEXT tokamak

Published:2019-09 Issue: Volume:146 Page:902-905
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Zhou Song^ORCID,Wang Nengchao^ORCID,Rao Bo,Huang Zhuo,Li Da,Li Mao^ORCID,Jia Ruo,Zhang Wei,Peng Shiyi,Song Zebao,He Ying,Yu Kexun,Ding Yonghua,Liang Yunfeng

Funder

National MCF Energy R&D Program of China

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference25 articles.

1. Developing and validating advanced divertor solutions on DIII-D for next-step fusion devices;Guo;Nucl. Fusion,2016

2. Results of high heat flux tests of tungsten divertor targets under plasma heat loads expected in ITER and tokamaks;Budaev;Phys. Atom. Nucl.,2016

3. Power and particle control;Loarte;Nucl. Fusion,2007

4. Experimental divertor physics;Pitcher;Plasma Phys. Controlled Fusion,1997

5. Inter-ELM power decay length for JET and ASDEX Upgrade: measurement and comparison with heuristic drift-based model;Eich;Phys. Rev. Lett.,2011

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4. Towards advanced divertor configurations on the J-TEXT tokamak;Plasma Science and Technology;2022-12-01

5. A brief review on the interaction between resonant magnetic perturbation and tearing mode in J-TEXT;Reviews of Modern Plasma Physics;2022-09-07