Zobrazeno 1 - 10
of 247
pro vyhledávání: '"V G, Baranov"'
Publikováno v:
Journal of Nuclear Materials. 475:266-273
Although uranium mononitride has a high melting point (≈3100 K), it often decomposes well below this temperature. The threshold and kinetics of thermal decomposition depend on samples' chemical content and on gas environment. However, most experime
Autor:
E. S. Solntseva, A. V. Tenishev, R S Kuzmin, M.L. Taubin, V. G. Baranov, V.A. Astafyev, V V Mikhalchik, S A Pokrovskiy
Publikováno v:
Annals of Nuclear Energy. 87:784-792
Thermochemical stability of nitride nuclear fuel is an important factor that ought to be considered in fabrication processes, operation and more importantly under accidental conditions. Development of a reliable technique which determines dissociatio
Autor:
V. I. Vybyvanets, E.S. Solntceva, V. G. Baranov, M.L. Taubin, I.E. Galyov, A. V. Tenishev, O.V. Homyakov
Publikováno v:
Annals of Nuclear Energy. 87:799-802
The comparative analysis of the results obtained by the authors of this paper and the available literature data on the thermal conductivity of uranium mononitride was prepared, analytical review of the thermal properties of mixed uranium–plutonium
Publikováno v:
Physics of Atomic Nuclei. 78:1345-1352
It is shown that a change in the linear dimension of compacted UO2 in the sintering process is associated with its plastic yielding under the action of the forces of residual stress and capillary forces. From the curves of sintering of a fuel with do
Publikováno v:
Tsvetnye Metally. :36-39
Autor:
A. V. Tenishev, E. S. Solntseva, V. I. Vybyvanets, M.L. Taubin, O. V. Khomyakov, I. E. Galev, V. G. Baranov
Publikováno v:
Atomic Energy. 117:257-264
The aims of this work were to compare the results of studies performed by the present authors using the existing data on the thermal conductivity of uranium mononitride and colligate and analyze the thermal conductivity of mixed uranium-plutonium fue
Publikováno v:
Advanced Materials Research. 1040:47-52
Thermal stability of the sintered samples of uranium mononitride was investigated in high purity helium atmosphere at 1900° – 2300°С. Thermogravimetry analysis of samples showed that the weight loss in uranium nitride consists of two stages. On
Publikováno v:
Journal of Nuclear Materials. 452:147-157
Experiments in IC-100 and U-400 cyclotrons were conducted with SIMFUEL pellets (11.47 wt.% of fission products simulators) to reproduce some aspects of the long-term irradiation conditions in epithermal reactors. Pellets were irradiated with Xe 16+ ,
Autor:
Mikhail Perlovich, Yuriy Perlovich, A. V. Tenishev, Margarita Isaenkova, Olga Krymskaya, V. G. Baranov
Publikováno v:
Advanced Materials Research. 996:701-706
Manufacture of fuel tablets from UO2 powder includes many processes, among which shrinkage without application of external loading till now requires explanations. Particles of UO2 are brittle up to ~ 700°C. By cold pressing due to the porous structu
Publikováno v:
Journal of Nuclear Materials. 434:248-251
Nitride fuel is one of perspective materials for the nuclear industry. But unlike the oxide and carbide uranium and mixed uranium–plutonium fuel, the nitride fuel is less studied. The present article is devoted to the development of a model for cal