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Kazakhstan Tokamak for Material Testing

Authors :
I.L. Tazhibaeva
N.Ya. Dvorkin
L. N. Tikhomirov
G. V. Shapovalov
V. A. Korotkov
A. B. Mineev
E. A. Azizov
I. N. Leykin
V.P. Shestakov
I. A. Kovan
E. P. Velikhov
V. A. Krylov
R.R. Khayrutdinov
V. N. Dokouka
V. S. Shkolnik
Source :
Plasma Devices and Operations. 11:39-55
Publication Year :
2003
Publisher :
Informa UK Limited, 2003.

Abstract

The Kazakhstan Tokamak for Material testing (KTM) is proposed as a test bench for plasma-facing components investigation. Special attention is devoted to divertor plates testing under powerful particle and heat flux deposition. There are two important pecularities of KTM, which make it a unique installation: - single null (SN) plasma configuration with moderate-to-low aspect ratio A=2, high elongation k 95 , 1.7 and megaampere level of plasma current IP ; creation of database for elongated plasma with A=2 can be an important "bridge" between databases on traditional tokamaks with A >2.5-3 and spherical tokamaks with A h 1.5-1.6; - special equipment is designed for manipulation with divertor plates (vacuum sluices, a divertor "table" inside the vacuum vessel, which can be shifted both in vertical and azimuth directions).

Details

ISSN :
10294929 and 10519998
Volume :
11
Database :
OpenAIRE
Journal :
Plasma Devices and Operations
Accession number :
edsair.doi...........489530351f67c30b67b9d570d1daa7a1
Full Text :
https://doi.org/10.1080/1051999031000088457