Commissioning and the first stage of physical start-up Tokamak KTM are conducted in 2017, in 2020 the complex KTM will be put in commission.

To date, following studies are conducted:

  • the process of forming plasma pinch of KTM Tokamak and output to a nominal parameters;
  • development of the methodical base to study the interaction of KTM plasma with materials on the simulation stand with plasma-beam installation;
  • preparation of the physical diagnostic and methodological complex to determine parameters of Tokamak KTM plasma;

Temperature changes of IRV on the vacuum stand under the sample heating up to 500 ºС

  • provision of KTM experiment with calculation methods, calculation codes of plasma modeling;
  • preparation, testing and development of HF, microwave methods of preionization and heating of KTM Tokamak plasma;
  • on testing and developing of operation modes of the lithium divertor mock-up based on capillary-porous system; interaction of KTM plasma with lithium and the effect of interaction of reactor irradiation on it;
  • effects of irradiation with charged particles and plasma on sputtering and thermal erosion of the surface, accumulation of gas impurities and changes in the mechanical properties of promising materials for the protection of the first wall of fusion reactor;
  • influence of radiation-induced internal stress gradients under irradiation with neutrons and charged particles on structural phase transformations and mechanical properties of austenitic stainless steels;
  • on the interaction of plasma with the surfaces of candidate materials of Tokamak KTM, occurring as a result of the failure of the plasma pinch;
  • according to the rules of capture of hydrogen isotopes by the materials of the first wall;
  • experimental and theoretical studies of the effects of plasma, hydrogen and helium ions on the near-surface and massive layers of KTM materials.
Mock-up of lithium divertor

In the framework of the CIS Intergovernmental Agreement on the joint use of Tokamak KTM, a program of scientific study on Kazakhstani Material Tokamak has been developed, which includes:

  • Conduction of studies on plasma physics;
  • Conduction of studies on the physics of plasma interaction with the materials of the first wall and the divertor of future fusion reactors;
  • Creation and testing of diagnostics to study the processes of plasma-wall interaction;
  • Material testing studies of structural and functional materials of future fusion reactors;
  • Research and implementation of new innovative technologies: “Development of operation modes of the mock-up of lithium divertor KTM”;
  • Development of automation, control and data collection systems, experimental verification of calculation codes.