High heat flux components in fusion devices: from current experience in Tore Supra towards the ITER challenge-Reference-Cited by-同舟云学术

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High heat flux components in fusion devices: from current experience in Tore Supra towards the ITER challenge

Published:2004-08 Issue: Volume:329-333 Page:909-913
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Grosman A,Bayetti P,Chappuis P,Cordier J.J,Durocher A,Escourbiac F,Guilhem D,Lipa M,Marbach G,Mitteau R,Schlosser J

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference18 articles.

1. Tore Supra steady-state power and particle injection: the ‘CIMES’ project

2. Brazed Graphite for Actively Cooled Plasma-Facing Components in Tore Supra — Description, Tests, and Performance

3. Toward Long-Pulse, High-Performance Discharges in Tore Supra: Experimental Knowledge and Technological Developments for Heat Exhaust

4. Power deposition and margins on the Tore Supra pump limiter and fabrication of the high heat flux components

5. J. Jacquinot, Proceedings of the 19th AIEA Fusion Energy Conference, Paper IAEA-CN-94/OV/1-2, 2002

Cited by 11 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. Study on onset of nucleate boiling with screw tube for fusion reactor application;Nuclear Fusion;2022-01-18

2. Composite Materials for Plasma-Facing Applications in Nuclear Fusion;Wiley Encyclopedia of Composites;2012-07-20

3. Heat flux calculation and problem of flaking of boron carbide coatings on the Faraday screen of the ICRH antennas during Tore Supra high power, long pulse operation;Fusion Engineering and Design;2011-06

4. Health monitoring of Tore-Supra Toroidal Pump Limiter using Lock-in thermography;Fusion Engineering and Design;2009-06

5. Improvement of the non-destructive evaluation of plasma facing components by data combination of infrared thermal images;NDT & E International;2007-09

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