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).