Zobrazeno 1 - 10
of 17
pro vyhledávání: '"V. V. Brovko"'
Autor:
V. V. Brovko, V. V. Tishkin, V. A. Bakshaev, N. P. Aleshin, M. V. Grigor’ev, N. A. Shchipakov
Publikováno v:
Inorganic Materials: Applied Research. 12:1047-1052
Agglomerations of oxide films are some of the typical defects of friction stir welding. The structure of such defects and their small opening do not allow finding them using the conventional ultrasonic nondestructive testing methods (in particular, b
Autor:
A. S. Pankratov, R. S. Mikheev, A. A. Linnik, N. V. Kobernik, V. V. Brovko, A. L. Galinovskii
Publikováno v:
Russian Metallurgy (Metally). 2018:1249-1254
The influence of the parameters of feeding and heating of an additional flux-cored electrode during machine hidden arc welding with an additional hot additive on the process is considered. Beads are deposited onto a 10-mm-thick steel (St3sp steel, GO
Autor:
A. S. Pankratov, V. V. Brovko, N. P. Aleshin, N. V. Alekseev, R. S. Mikheev, N. V. Kobernik, A. A. Linnik, S. A. Shtokolov, A. V. Samokhin, M. A. Sinayskiy
Publikováno v:
Russian Metallurgy (Metally). 2018:820-825
The influence of nanoparticles introduced into a molten weld pool using a flux-cored wire on the structure and impact toughness of the weld metal is considered. The use of a flux-cored wire with tungsten carbide particles is shown to decrease the sca
Autor:
A. S. Korol'kov, Yu. M. Pevchikh, B. D. Rogozkin, V. N. Leonov, A. I. Filin, V. V. Brovko, A. G. Sila-Novitskii, A. D. Yurchenko, V. N. Efimov, A.A. Pikalov, P. N. Martynov, K. D. Ivanov, A. A. Ryzhov, A. G. Kordyukov, Yu. A. Kostyukov, Yu. I. Orlov, V. M. Troyanov, Yu. E. Stynda
Publikováno v:
Atomic Energy. 97:564-570
A special feature of the BREST-OD-300 reactor that is now being designed is that it employs a container-type heat-conducting fuel element with mixed uranium–plutonium mononitride fuel, a lead sublayer, and an expansion volume at the top to collect
Publikováno v:
Welding International. 13:473-477
Publikováno v:
Journal of Nuclear Materials. :305-308
Weld joints in 11–14% Cr steels were studied after their exposure in fast reactor at 70–550°C at damaging doses up to 40 dpa. Independent of the phase and chemical compositions weld joints as in-pile irradiated at temperatures below 400°C are s
Autor:
V. V. Brovko, V. N. Leonov, Yu. E. Shtynda, A. I. Filin, V. M. Troyanov, Yu. M. Pevchikh, Yu. I. Orlov, P. N. Martynov, A. A. Ryzhov, A. G. Sila-Novitsky, A.A. Pikalov, B. D. Rogozkin, Konstantin Dmitrievich Ivanov, Yu. A. Kostyukov, A. D. Yurchenko, V. N. Yefimov, A. S. Korol'kov
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). 2003:174
Publikováno v:
Welding International. 3:52-54
Publikováno v:
Chemischer Informationsdienst. 6
Publikováno v:
Chemischer Informationsdienst. 5