Properties of co-deposited layers on graphite high heat flux components at the TEXTOR tokamak-Reference-Cited by-同舟云学术

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Properties of co-deposited layers on graphite high heat flux components at the TEXTOR tokamak

Published:2007-08 Issue: Volume:367-370 Page:1507-1511
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Fortuna E.,Rubel M.J.,Philipps V.,Kurzydłowski K.J.,Mertens Ph.,Miśkiewicz M.,Pisarek M.,Van Oost G.,Zieliński W.

Publisher

Elsevier BV

Subject

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

Reference13 articles.

1. Erosion and redeposition of wall material in controlled fusion devices

2. Plasma wall interaction and tritium retention in TFTR

3. In-situ observation of the chemical erosion of graphite in the scrape-off-layer of TEXTOR

4. M. Rubel, P. Wienhold, in: K.H. Spatschek, J. Uhlenbusch (Eds.), Akademie Verlag, Berlin, 1994, Chapter 5.8.

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. Review on global migration, fuel retention and modelling after TEXTOR decommission;Nuclear Materials and Energy;2018-12

2. Fine metal dust particles on the wall probes from JET-ILW;Physica Scripta;2017-10-24

3. Dust survey following the final shutdown of TEXTOR: metal particles and fuel retention;Physica Scripta;2016-01-21

4. First dust study in JET with the ITER-like wall: sampling, analysis and classification;Nuclear Fusion;2015-09-01

5. Research on laser-removal of a deuterium deposit from a graphite sample;Journal of Physics: Conference Series;2014-04-24

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