Zobrazeno 1 - 10
of 37
pro vyhledávání: '"V. N. Proselkov"'
Publikováno v:
Atomic Energy. 122:15-18
The results of modeling VVER-1000 fuel elements, performed using a fuel-element energy release restoration module integrated into the ATHLET/BIPR-VVER software system, are presented. The results are presented for the example of the calculation of a r
Autor:
A. A. Dudnikov, A. S. Sumarokova, A. Yu. Smirnov, G. A. Sulaberidze, V. A. Nevinitsa, P. A. Fomichenko, V. N. Proselkov
Publikováno v:
Atomic Energy. 119:291-296
This scientifi c and technical communication examines the physical mechanisms of the change in the isotopic composition of regenerated uranium recycled in VVER-1000 and -1200 fuels. Modeling of the Multiple Recycling of Regenerated Uranium. An approa
Publikováno v:
Atomic Energy. 114:94-101
The results of development work on the base five-year fuel cycles with second-generation cassettes and average enrichment 4.87% for NPP with VVER-440 are presented. Such power units make it possible to increase thermal power while preserving an accep
Autor:
P. N. Alekseev, A. A. Dudnikov, V. N. Proselkov, A. V. Chibinyaev, A. Yu. Smirnov, G. A. Sulaberidze, V. A. Nevinitsa
Publikováno v:
Physics of Atomic Nuclei. 75:1616-1625
A complex approach based on the consistent modeling of neutron-physics processes and processes of cascade separation of isotopes is applied for analyzing physical problems of the multiple usage of reprocessed uranium in the fuel cycle of light water
Publikováno v:
High Temperature. 50:221-224
Thermodynamic models of a UO2-based melt and cubic solid solution were developed on the basis of the most accurate measurements of the UO2-Gd2O3 liquidus in a range of 0–30 mol. % of Gd2O3. These models enabled computing the phase diagram of this s
Publikováno v:
Atomic Energy. 108:155-164
A long series of computational works validating possibilities for improving of VVER-440 fuel cycles has been completed at the Russian Science Center Kurchatov Institute. Work was performed on upgrading and improving VVER-440 fuel cycles on the basis
Autor:
V. N. Proselkov, S. G. Popov
Publikováno v:
High Temperature. 47:514-526
Analytical expressions are given for the phase boundaries of diagrams of state for Zr-Nb and Zr-Sn systems. Thermodynamically justified temperature dependences of heat capacity of Zr-1% Nb, Zr-2.5% Nb, Zr-1.5% Sn, and Zr-2.5% Sn alloys in two-phase r
Publikováno v:
Atomic Energy. 101:869-875
The results of calculations performed with the PINw99, TRANSURANUS (V1M1V03), and TOPRA-2 computer programs are compared with data obtained from post-reactor investigations of fuel elements which operated for four years in the No. 1 unit of the Zapar
Publikováno v:
Atomic Energy. 101:790-796
A method of performing stationary thermomechanical calculations of VVER-440 and-1000 fuel elements, using the TRANSURANUS computer code to obtain the dependence of the temperature and radius of the fuel elements on the lineal power ensity and burnup,
Autor:
S. G. Popov, V. N. Proselkov
Publikováno v:
Atomic Energy. 99:451-463
Recommended analytical relations for phase boundaries in the system Zr-Nb, heat capacity of the alloys Zr-1%Nb and Zr-2.5%Nb in two-phase regions α-Zr + β-Zr and β-(Zr, Nb) + liquid are presented. The integral heat of the phase transformations α-