Zobrazeno 1 - 10
of 32
pro vyhledávání: '"I. Alekseev"'
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:
Anastasiia Leonteva, Natalia Gubanova, Vladimir Bedran, Sergey Miklyaev, Maksim V. Manzuk, F. Milani, D. I. Alekseev, Konstantin Bestuzhev, Alexander Roshal
Publikováno v:
Fusion Engineering and Design. 146:2772-2776
In ITER, each circuit of the central solenoid as well as poloidal field coils PF1 and PF6 is provided with a system for plasma initiation, called the Switching Network Unit (SNU), able to supply voltage up to 8.5 kV for the coils. This will be obtain
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. 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. 116:72-75
Autor:
V. V. Petrunin, Yu. P. Sukharev, V. I. Alekseev, S. N. Pichkov, S. E. Sorokin, S. L. Osipov, V. N. Vavilkin, R. A. Peskov
Publikováno v:
Atomic Energy. 114:157-160
The effect of small additions of Np, Am, and Cm to fresh uranium fuel on the critical mass, heat release, intensity of the spontaneous neutron radiation, and radiation dose rate, i.e., on the characteristics determining the attractiveness of the fuel
Publikováno v:
Atomic Energy. 112:67-71
Publikováno v:
Atomic Energy. 105:159-164
The principles used in the design of low- and medium-power nuclear power systems to decrease the proliferation risk for nuclear materials as well as the results of a comparative analysis of GT-MGR, KLT-40, ABV, and foreign-produced light-water PWRs f
Publikováno v:
Atomic Energy. 104:1-4
To develop new-generation enhanced-safety VVER-1200 reactor with improved technical performance and cost effectiveness for AES-2006, it is necessary to increase the accuracy of the programs used to calculate the neutron-physical characteristics. Benc
Autor:
Yu. A. Epanechnikov, A. A. Ognev, V. Yu. Aborin, Yu. A. Krainov, A. D. Klochkov, S. S. Gorodkov, V. R. Ostrovskii, N. I. Alekseev, Yu. M. Semchenkov, I. N. Aborina
Publikováno v:
Atomic Energy. 93:790-799
A series of investigations studying the currents of rhodium sensors in in-reactor monitoring systems and the relation between the currents and the energy release in the fuel elements in the nearest neighbor environment in a VVER-1000 fuel assembly mo