Kazakhstan Tokamak for Material Testing

Энглен Атакузиевич Азизов, V. N. Dokouka, N.Ya. Dvorkin, Rustam R. Khayrutdinov, V. A. Korotkov, I. A. Kovan, В. А. Крылов, I. N. Leykin, Anatolij B. Mineev, G.V. Shapovalov

5 more authors

Vladimir P. Shestakov, V. S. Shkolnik, Irina L. Tazhibaeva, L. N. Tikhomirov, Evgeny Pavlovich Velikhov

2003

Closed access Metadata (CSL-JSON)

DOI 10.1080/1051999031000088457

Data confidence 70 medium

How this score is calculated

It is built from checkable properties of the record itself: whether the article has a DOI, how many independent sources confirmed its data, whether the required fields are filled in, and how recent the latest confirmation is. Disagreement between sources and a missing identifier lower it. A value of 80 or above means the record was published without further checking; 60 to 79 means it is published at reduced confidence, with a manual check advisable. A record verified by an editor by hand is never pushed below 90 by a recalculation. This scores our data about the article, not the article itself.

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).