Zobrazeno 1 - 10
of 16
pro vyhledávání: '"S. L. Osipov"'
Autor:
Sergey A. Rogozhkin, Andrey A. Aksenov, Sergey V. Zhluktov, S. L. Osipov, I. D. Fadeev, Elena V. Shaporenko, Sergey F. Shepelev, Vladimir V. Shmelev
Publikováno v:
Компьютерные исследования и моделирование, Vol 6, Iss 6, Pp 923-935 (2014)
The possibility to study temperature fluctuations using URANS approach is studied. The results of numerical simulation of mixing processes for triple-jet sodium at different temperatures are presented. The processes were simulated using FlowVision so
Externí odkaz:
https://doaj.org/article/516e9e901de54847ba9c0c9a7d30a1cb
Publikováno v:
Atomic Energy. 128:245-250
Methods of determining the efficiency of the system that controls the seal-tightness of fuel-rod cladding and localizes FA with leaky fuel rods in a fast reactor are examined. It is shown that the design procedure has significant limitations. A proce
Autor:
V. M. Alipchenkov, Yu. A. Zeigarnik, N. A. Mosunova, E. F. Seleznev, D. A. Afremov, P. V. Kolobaeva, V. S. Gorbunov, E. V. Moiseenko, A. A. Semchenkov, S. L. Osipov, D.P. Veprev, A. V. Boldyrev, E. V. Usov, Valery F. Strizhov
Publikováno v:
Thermal Engineering. 65:627-640
The article presents information on the validation and verification (V&V) of the first version (V1) of the EUCLID integrated code intended for safety analysis of operating or designed liquid metal (sodium, lead, or lead–bismuth) cooled reactors und
Autor:
A. M. Veremeev, S. I. Porollo, S. V. Zabrodskaya, V. M. Poplavskii, L. I. Moseev, S. L. Osipov, A. G. Tsikunov
Publikováno v:
Atomic Energy. 122:390-395
The key experimental and computational studies of the emission of long-lived radioactive fission products and actinides from uranium dioxide irradiated in BN-600 into sodium and the gas phase in the range 150–800°C, performed on the experimental b
Autor:
I. A. Klimonov, A. M. Anfimov, Valery F. Strizhov, E. V. Usov, D. V. Kuznetsov, N. A. Mosunova, S. L. Osipov, A. A. Butov, A. I. Bel’tyukov, I. G. Kudashov, V. S. Gorbunov, G. A. Dugarov, E. N. Ivanov
Publikováno v:
Atomic Energy. 122:311-318
The results of thermohydraulic code HYDRA-IBRAE/LM/V1 verification on experimental data obtained using the BN-600 reactor in different years are described. The particulars of the computational scheme of the reactor using HYDRA-IBRAE/LM/V1 for modelin
Autor:
V. V. Pakholkov, B. V. Kebadze, V. A. Shurupov, M. A. Gubyrin, A. N. Kryukov, E. A. Mumrenkov, A. N. Fomin, E. L. Rozenbaum, S. V. Bogatov, S. L. Osipov, A. A. Lagutin, V. P. Shokhonov, E. V. Generalov
Publikováno v:
Atomic Energy. 122:29-34
The presented systems are intended for measuring the sodium flow through the main circulation pumps in the first loop and FA in BN-800. The systems are identical in terms of structure and contain two electromagnetic and one correlation channel. A com
Autor:
V. S. Gorbunov, Vladimir M. Alipchenkov, A. M. Anfimov, E. V. Usov, Yu. A. Zeigarnik, N. A. Mosunova, D. A. Afremov, S. L. Osipov, Valery F. Strizhov, A. V. Kudryavtsev
Publikováno v:
Thermal Engineering. 63:130-139
The conceptual fundamentals of the development of the new-generation system thermal-hydraulic computational HYDRA-IBRAE/LM code are presented. The code is intended to simulate the thermalhydraulic processes that take place in the loops and the heat-e
Computational and Experimental Studies Substantiating Setups for Localizing Fast-Reactor Melted Fuel
Autor:
A. A. Kozhaev, M. S. Mavrin, S. A. Rogozhkin, Sergey F. Shepelev, A. A. Ryabov, S. L. Osipov, V. A. Sobolev
Publikováno v:
Atomic Energy. 115:416-421
Autor:
I. D. Fadeev, S. L. Osipov, S. V. Zhluktov, Andrey A. Aksenov, Sergey F. Shepelev, S. A. Rogozhkin, Vladimir V. Shmelev, M. L. Sazonova
Publikováno v:
Atomic Energy. 115:357-361
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