Zobrazeno 1 - 7
of 7
pro vyhledávání: '"E. V. Marova"'
Autor:
B. A. Vasil’ev, A. V. Vasyaev, Yu. M. Ashurko, D. A. Klinov, S. F. Shepelev, A. V. Gulevich, E. V. Marova
Publikováno v:
Atomic Energy. 125:351-358
The design of the BN-1200 sodium-cooled fast reactor is analyzed from the standpoint of its compliance with the criteria fitting the promising Gen-IV reactor facilities. The basic technical solutions adopted in the BN-1200 design making it possible t
Publikováno v:
Nuclear Engineering and Design. 382:111384
Autor:
V. P. Garin, N. N. Ponomarev-Stepnoi, Yu. P. Sukharev, E. S. Glushkov, O. N. Smirnov, A. S. Ponomarev, V. A. Nevinitsa, G. V. Kompaniets, V. F. Boyarinov, A. A. Zimin, P. A. Fomichenko, E. V. Marova, E. I. Chunyaev, D. N. Polyakov
Publikováno v:
Physics of Atomic Nuclei. 73:2290-2295
The paper presents the results obtained from the computational/experimental studies of the spatial distribution of the 235U fission reaction rate in a critical assembly with an annular core and poison profiling elements inserted into the inner graphi
Publikováno v:
Atomic Energy. 102:82-85
The results of a computational investigation of the neutron-physical characteristics and parameters of GT-MHR for different fuels are presented: weapons-grade plutonium, reactor plutonium, low-enrichment uranium, mixed fuel based on uranium and weapo
Autor:
V. F. Boyarinov, V. D. Davidenko, N. V. Novikov, E. S. Glushkov, P. A. Fomichenko, E. F. Mitenkova, V. F. Tsibul’skii, G. V. Kompaniets, V. I. Bryzgalov, M. I. Gurevich, Yu. P. Sukharev, V. A. Nevinitsa, A. M. Krutov, N. G. Kodochigov, E. A. Gomin, M. S. Yudkevich, E. V. Marova
Publikováno v:
Atomic Energy. 102:75-81
The main results of computational and experimental investigations of the neutron-physical characteristics of the GT-MHR high-temperature gas-cooled reactor are presented: analysis of the possible reasons for the uncertainties in the calculations of t
Autor:
N. Ponomarev-Stepnoy, P. A. Fomichenko, Yu.P. Sukharev, E. V. Marova, N. G. Kodochigov, E. S. Glushkov
Publikováno v:
Nuclear Engineering and Design. 222:161-171
The design of a Gas Turbine–Modular Helium Reactor (GT-MHR) of 600 MWt power is being developed in frames of “The Agreement between the Government of the United States of America and the Government of the Russian Federation on Scientific and Tech
Autor:
C. Ellis, N. Ponomarev-Stepnoy, E. V. Marova, P. A. Fomichenko, E. S. Glushkov, N. G. Kodochigov, Yu.P. Sukharev
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 4.
The GT-MHR reactor core is characterized by flexibility of neutronic characteristics at the given average power density and fixed geometrical dimensions of reactor core. Such flexibility makes it possible to start the reactor operation with one fuel