Kazakhstan Tokamak for Material Testing

• Published in: Plasma devices and operations Vol. 11; no. 1; pp. 39 - 55
• Main Authors: Azizov, E. A., Dokouka, V. N., Dvorkin, N. Ya, Khayrutdinov, R. R., Korotkov, V. A., Kovan, I. A., Krylov, V. A., Leykin, I. N., Mineev, A. B., Shapovalov, G. V., Shestakov, V. P., Shkolnik, V. S., Tazhibaeva, I. L., Tikhomirov, L. N., Velikhov, E. P.
• Format: Journal Article
• Language: English
• Published: Taylor & Francis Group 2003
• Subjects: Divertor; Plasma-facing Components; Tokamak; Toroidal Field Coil; Vacuum Vessel
• ISSN: 1051-9998; 1029-4929
• DOI: 10.1080/1051999031000088457

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 I P ; 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).