Progress in the design and development of a test divertor (TDU) for the start of W7-X operation-Reference-Cited by-同舟云学术

Progress in the design and development of a test divertor (TDU) for the start of W7-X operation

Published:2009-06 Issue:7-11 Volume:84 Page:1475-1478
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Peacock A.,Greuner H.,Hurd F.,Kißlinger J.,König R.,Mendelevitch B.,Stadler R.,Schauer F.,Tivey R.,Tretter J.,von Sehren C.,Ye M.

Publisher

Elsevier BV

Subject

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

Reference5 articles.

1. J. Kißlinger, C. Beidler, E. Harmeyer, F. Rau, H. Renner, H. Wobig, Proceedings of 21st European Conference on Controlled Fusion and Plasma Heating, Montpellier, vol. 18C Part I, European Physical Society, 1994.

2. First island divertor experiments on the W7-AS stellarator;Grigull;Plasma Phys. Control. Fusion,2001

3. Divertor operation in stellarators: results from W7-AS and implications for future devices;Grigull;Fusion Eng. Des.,2003

4. High heat flux facility GLADIS:

5. R. Stadler, A. Vorköper, J. Boscary, A. Cardella, F. Hurd, C. Li, et al., Fusion Eng. Des. (2009), in press.

Cited by 40 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Conceptual design of the next generation of W7-X divertor W-target elements;Fusion Engineering and Design;2023-07

2. Assessment of carbon net erosion/deposition at the divertor of W7-X;Nuclear Materials and Energy;2023-03

3. Carbon erosion/deposition on the divertor of W7-X during the operational period OP 1.2b;Nuclear Fusion;2022-10-31

4. Erosion of tungsten marker layers in W7-X;Physica Scripta;2021-12-01

5. Wendelstein 7-X on the path to long-pulse high-performance operation;Fusion Engineering and Design;2021-06