New Version of the KTM Lithium Divertor

At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithiu...

Full description

Saved in:
Bibliographic Details
Published in:Physics of atomic nuclei 2020-12, Vol.83 (7), p.1116-1123
Main Authors: Vertkov, A. V., Zharkov, M. Yu, Lyublinski, I. E., Berlov, A. V., Tazhibayeva, I. L., Ponkratov, Yu. V., Gordienko, Yu. N.
Format: Article
Language:English
Subjects:
Alloys
Coolants
Cooling systems
Design optimization
Eutectic alloys
Heat transfer coefficients
Heat transmission
Liquid metals
Lithium
Modules
Nuclear energy
Particle and Nuclear Physics
Physics
Physics and Astronomy
Product enhancement
Tokamak devices
Tokamaks
Water flow
Water sprays
Citations: Items that this one cites
Items that cite this one
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithium capillary porous systems has been developed and tested successfully in real tokamak conditions. In this design, the problem of removing high-density heat flows is solved by using liquid metal coolant based on the Na–K eutectic alloy. The requirements for the improved safety and the divertor design compatibility with other in-vessel water-cooled elements of the tokamak and temperature limitation of the receiving lithium surface to the level
ISSN:1063-7788
1562-692X
DOI:10.1134/S1063778820070121