Behaviour of a tungsten coated molybdenum poloidal limiter in FTU tokamak
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference16 articles.
1. A comparison of lifetimes of beryllium, carbon, molybdenum and tungsten as divertor armour materials
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3. Evaluation of tungsten as a plasma-facing material for steady state magnetic fusion devices
4. Optimization of the FTU toroidal limiter shape
5. M.L. Apicella et al., Plasma characteristics in FTU with different limiter materials, ENEA Report RT/ERG/FUS/95/19, Nucl. Fussion, accepted.
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1. Selection of molybdenum lines by quantitative analysis of molybdenum- zirconium-titanium alloy by CF-LIBS for future fusion applications;Fusion Engineering and Design;2020-04
2. Recrystallization and grain growth behavior of rolled tungsten under VDE-like short pulse high heat flux loads;Journal of Nuclear Materials;2013-02
3. Divertor tungsten tile melting and its effect on core plasma performance;Nuclear Fusion;2012-10-30
4. Chapter 4: Power and particle control;Nuclear Fusion;2007-06
5. Thermal Spray Coatings for Fusion Applications—Review;Journal of Thermal Spray Technology;2007-03-14
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