TRIEX-II: An experimental facility for the characterization of the tritium extraction unit of the WCLL blanket of ITER and DEMO fusion reactors

TRIEX-II: An experimental facility for the characterization of the tritium extraction unit of the WCLL blanket of ITER and DEMO fusion reactors

The experimental qualification of the tritium extraction unit (TEU) from the LiPb eutectic alloy (15.7 at. % Li), the breeder material of the water-cooled lithium-lead breeding blanket concept, is one of the fundamental items for the demonstration of tritium balance sustainability for ITER and DEMO...

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Bibliographic Details
Main Authors: Alberghi, C. (Author), Candido, L. (Author), Papa, F. (Author), Tarantino, M. (Author), Utili, M. (Author), Venturini, A. (Author)
Format: Article
Language:English
Published: IOP Publishing Ltd 2022
Subjects:
Binary alloys
Breeder reactors
Breeding blankets
Experimental facilities
Extraction
Extraction systems
Fusion reactors
gas-liquid contactor
Gas-liquid contactors
Helium
Hydrogen
Liquids
liquid-vacuum contactor
Liquid-vacuum contactor
Lithium
Lithium alloys
Lithium-lead
permeation against vacuum
Permeation against vacuum
TRIEX-II
Tritium
Tritium extraction
tritium extraction system
Tritium extraction system
Vacuum contactors
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