Tokamak KTM complex for material investigation

The experimental complex on the basis of spherical tokamak KTM is intended to study and test the first wall materials and designs of divertor plates constructions of reactor-tokamak, to try out the methods for reducing loads at a divertor and various methods of heat- and energy removal, as well as the methods of fast exhaust of divertor volume and development of the methods to prevent failures of intrachamber components. Parameters of energy loads and wide range of the used methods and diagnostics allow for studies and testings in the divertor space and at the first wall, which will be of great importance for the study of plasma facing materials in ITER and DEMO project, as well as for other experimental and power fusion reactors. The paper contains basic parameters of spherical tokamak KTM, test bench for simulations, plasma-physical and material test tasks and KTM project status activity. The activities of 2007-2008 are aimed at completion of the tokamak construction, and commissioning of the facility, including delivery of the equipment to KTM site, installation of the complex technological systems, mounting of impulse supply system, and commissioning of the facility. The potentials are being discussed to use the tokamak KTM as a physical prototype for the compact fusion power unit with warm electromagnetic system. (author)