Erosion and deposition at the ALT-II limiter of TEXTOR
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference15 articles.
1. Hydrogen inventories in nuclear fusion devices
2. Analysis and oxidation of thick deposits on TEXTOR plasma facing components
3. Properties of Thick Layers Deposited on Plasma Facing Wall Components of TEXTOR-94
4. Wall erosion and material transport to the Mark I carbon divertor of JET
Cited by 8 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. Migration and balance of 13C in the stellarator Wendelstein 7-X after 13CH4 local injection into the island divertor;Nuclear Materials and Energy;2024-06
2. Long-term carbon transport and fuel retention in gaps of the main toroidal limiter in TEXTOR;Journal of Nuclear Materials;2013-07
3. Effect of surface roughness and substrate material on carbon erosion and deposition in the TEXTOR tokamak;Plasma Physics and Controlled Fusion;2008-07-24
4. Long-term erosion and deposition studies of the main graphite limiter in TEXTOR;Physica Scripta;2007-03
5. Simulation of redeposition patterns of hydrocarbons released from carbon target in divertors;Fusion Engineering and Design;2006-02
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