Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation-Reference-Cited by-同舟云学术

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Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation

Published:2007-10 Issue:15-24 Volume:82 Page:2390-2398
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Grisolia C.,Counsell G.,Dinescu G.,Semerok A.,Bekris N.,Coad P.,Hopf C.,Roth J.,Rubel M.,Widdowson A.,Tsitrone E.

Publisher

Elsevier BV

Subject

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

Reference35 articles.

1. Conditioning procedures in Tokamak: Tore Supra application

2. Tritium retention of plasma facing components in tokamaks

3. Tritium Removal from Carbon Plasma Facing Components

4. Possible techniques for the detritiation of first wall materials from fusion machines

5. Is carbon a realistic choice for ITER's divertor?

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3. Laser induced breakdown spectroscopy application in joint European torus;Spectrochimica Acta Part B: Atomic Spectroscopy;2016-09

4. Cleaning of carbon materials from flat surfaces and castellation gaps by an atmospheric pressure plasma jet;Fusion Engineering and Design;2016-02

5. Picosecond LIBS diagnostics for Tokamakin situplasma facing materials chemical analysis;Physica Scripta;2016-01-12

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