Demo Project in Russia

B.N. Kolbasov, A.A. Borisov, N.N. Vasiliev, V.M. Leonov, G.Ye. Shatalov (RRC “Kurchatov Institute”,
V. A. Beliackov, A. N. Bondarchuk, I.R. Kirillov (NIIEFA named after D.V. Efremov, STC “Sintez”),
Yu.A. Sokolov (IAEA), Yu.S. Strebkov (NIKIET named after N.A. Dollexhal).

Conceptual design research of thermonuclear energy reactors on the basis of tokamak started in Russia in 1991.
The most preferable ones were the concepts of the reactor-tokamaks operating in the steady-state regime with
superconducting magnets, single-null divertor, and great contribution of bootstrap-current into retention of plasma
current. Two blanket concepts were analyzed: helium-cooled blanket with the use of Li4SiO4 ceramics for
reproduction of tritium, and ferritic steel as the structural material; as well as the blanket using liquid lithium for
reproduction of tritium and as the coolant, vanadium-chromium-titanium alloy was used as the structural material.
Ordinary water- or lithium-cooled divertor targets, which take thermal load of up to 10 MWt year/m2 were selected.
Blankets of both types require replacement of removable elements after thermonuclear neutron integral flux equivalent
to 10 MWt year/m2 is achieved. They also require use of beryllium for neutron multiplication. Results of the performed
analysis indicate the necessity of additional research to be carried out prior to selecting the most advanced blanket
concept for further development. We also investigate the issues of radioactive waste management, and of returning
deficit materials into production cycle.

The information is published by authority of founders.


Concept of the demonstrational thermonuclear energetic Reactor (in Russian)