V. Tebus

发表

A STUDY OF TRITIUM RELEASE AND PERMEABILITY UNDER IN-PILE IRRADIATION OF LI-PB EUTECTIC

A. Antonov, V. Tebus, V. Demidov, 1994 .

Prospects and problems using vanadium alloys as a structural material of the first wall and blanket of fusion reactors

M. I. Solonin, S. E. Bougaenko, V. Chernov, 1996 .

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

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

Vanadium alloys as structural materials for fusion reactor blanket

M. I. Solonin, V. I. Khrustalev, A. B. Alekseev, 1996 .

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 .

Breeding zone models of demo ceramic helium cooled blanket test module for reactor in-pile testing

A. Lopatkin, V. Muratov, D. Davydov, 2004 .

RITM-F facility

V. Tebus, V. Demidov, A. Zyrianov, 2004 .

Research and development of lithium ceramics and models of tritium breeding zones for blankets in Russian reactor projects

V. Tebus, V. Demidov, V. Kapyshev, 2004 .

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

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