ENGINEERING AND PHYSICAL ASSESSMENT OF TOKAMAK-15 RECONSTRUCTION
The paper deals with plans and opportunities to reconstruct and restart the superconducting tokamak T-15 during the time interval from 2008 up to 2022 years. It also reviews physical and technological programs of the project realizing in frames of Russian national fusion program. The reconstruction is aimed at reaching steady state operation with 1 MA current and plasma parameters as follows: the plasma density up to 10<sup>20</sup> m"<sup>3</sup>, ion temperature up to 10 keV, confinement time up to 0.3 s, those being close to the breakeven conditions. These objectives will be reached using the existing toroidal magnetic field coils and vacuum chamber accompanied by new poloidal field coils, which will make possible separatrix magnetic configuration (major radius <i>R </i>=2.43 m, minor radius 45 cm, aspect ratio <i>A </i>= 5.8, elongation <i>к = </i>1.4, triangularity 0.25). A poloidal divertor is designed to be capable to collect the heat loads up to 10 MW/m<sup>2</sup> provided by heating and current drive systems with total power higher than 20 MW including NBI (9 MW, 60 kV), ECRH (7 MW), LHCD (4 MW), ICRH (4 MW). Sequential increase in the pulse length from 5 to 30 and finally to 1000 s is planned. The T-15 reconstruction and restart will allow conducting research in support of the international ITER project as well as of Russian projects of fusion power plants.