Zobrazeno 1 - 10
of 42
pro vyhledávání: '"O. B. Samoilov"'
Autor:
G. V. Kulakov, Yu. V. Konovalov, A. V. Vatulin, A. A. Kosaurov, V. Yu. Shishin, A. A. Shel’dyakov, A. I. Romanov, O. A. Morozov, O. B. Samoilov
Publikováno v:
Atomic Energy. 130:220-223
Autor:
V. S. Ustinov, V. Yu. Galitskikh, A. N. Volkov, O. A. Morozov, V. I. Alekseev, S. A. Polyanskikh, O. B. Samoilov
Publikováno v:
Atomic Energy. 130:69-75
The physical aspects and main results of reactor tests of a two-stage core consisting of fresh fuel assemblies and a significant number of fuel assemblies from the previous core, which are left for re-burning on the KV-1 test facility in a 3+ run, ar
Autor:
O. B. Samoilov, D. L. Shipov, V. V. Petrunin, A. V. Kupriyanov, G. Sh. Iksanova, A. A. Zakharychev, A. B. Osin
Publikováno v:
Atomic Energy. 130:63-68
Autor:
B. A. Vasil’ev, V. V. Patrunin, M. A. Kamnev, O. B. Samoilov, S. V. Babushkin, A. M. Bakhmet’ev, S. N. Pichkov, N. G. Kodochigov, D. L. Zverev, N. G. Sandler
Publikováno v:
Atomic Energy. 129:66-73
Testing and experimental substantiation are a significant and integral part at all phases of the life cycle of reactor equipment. The Research and Testing Complex (RTC) operates at OKBM Afrikantov to ensure that these tasks are successfully fulfilled
Autor:
A. V. Kupriyanov, T. Yu. Vishneva, A. A. Molodtsov, D. L. Shipov, D. V. Doronkov, A. B. Osin, A. E. Khrobostov, S. M. Dmitriev, O. N. Morozkin, E. V. Sholin, O. B. Samoilov
Publikováno v:
Atomic Energy. 128:17-23
The results of studies of the intensification of heat-and-mass transfer and mixing of coolant are presented. Justification is given for the design, number, and arrangement of intermediate intensifier plate grids in combination with honeycomb spacer g
Autor:
O. B. Samoilov, A. G. Promokhov, V. Yu. Silaev, O. A. Morozov, V. I. Alekseev, V. I. Makarov, E. A. Dvoinishnikov
Publikováno v:
Atomic Energy. 126:21-28
The developmental history of the series-produced core for nuclear icebreakers and its conceptual and structural designs and the computational-methodological base of the physical design are presented. The fundamental differences from VVER-type power r
Autor:
S. M. Dmitriev, A. E. Khrobostov, A. N. Pronin, V. D. Sorokin, M. A. Legchanov, A. S. Noskov, O. B. Samoilov, D. N. Solntsev, A. A. Dobrov, D. L. Shipov, D. V. Doronkov
Publikováno v:
Thermal Engineering. 66:243-248
The experimental investigation of local hydrodynamic characteristics of the coolant flow downstream of a mixing spacer grid (MSG) in characteristic regions of a Kvadrat fuel assembly in PWRs was performed. The importance of this investigation is due
Autor:
S. G. Ust’yantsev, O. B. Samoilov, V. Yu. Galitskikh, A. V. Belin, V. I. Alekseev, V. V. Samusenkov, A. N. Zaglyadnov
Publikováno v:
Atomic Energy. 121:389-396
The results of experimental investigations of the spatial and energy distributions of the thermal and epithermal neutrons in a cassette fuel assembly, similar in design to that developed for the RITM-200 reactor core in the universal nuclear icebreak
Publikováno v:
Atomic Energy. 121:371-376
The tightness of fuel-element cladding is monitored in order to identify fuel assemblies where depressurization has occurred in the course of operation. The condition of the fuel elements in the fuel assemblies of icebreaker cores is determined durin
Publikováno v:
Atomic Energy. 120:335-341
Methods of validating the thermomechanical reliability of the core of water-moderated and -cooled reactors that are used in reactor design practice are reviewed. The factors determining the thermomechanical reliability of the core and the particulars