V. Frolov

发表

Metallurgical application of hydrogen-containing gases produced by the plasma coal gasification process at an environmentally clean thermal power station

G. Nozdrenko, V. Frolov, I. B. Frolova, 1993 .

Model and Mockup of DEMO Ceramic Breeding Zone for Testing in the IVV-2M Reactor

A. Lopatkin, V. Gorokhov, A. Shikov, 2001 .

Materials and fabrication technology of modules intended for irradiation tests of blanket tritium-breeding zones in Russian fusion reactor projects

V. Gorokhov, A. Shikov, Y. Strebkov, 2000 .

Models of Ceramic Tritium Breeding Zones in the Blanket of a Thermonuclear Reactor

E. A. Medvedeva, V. Gorokhov, A. Shikov, 2000 .

Radiation of lithium aluminate, lithium ortho-and metasilicate tablets in thermonuclear reactor and study of their GAS emission and strength properties

V. Kapyshev, V. Frolov, E. P. Starshin, 1994 .

Influence of neutron irradiation on the strength characteristics of lithium ceramic pellets for fusion reactor blankets

V. Tebus, V. Frolov, V. Kapychev, 2002 .

Radiation safety of the iter tritium fuel cycle

D. K. Kurbatov, E. Sergeev, V. Kapyshev, 1995 .