Zobrazeno 1 - 10
of 10
pro vyhledávání: '"D. M. Soldatkin"'
Publikováno v:
Atomic Energy. 132:219-222
Publikováno v:
High Temperature. 55:914-921
The reflooding investigations of large-scale model fuel assemblies and sphere beds under Design Basis Accident and Beyond Design Accident of Light Water Reactors WWER and PWR are presented. The generalizing correlation on the quench front velocity fo
Publikováno v:
Atomic Energy. 120:361-365
Publikováno v:
Journal of Physics: Conference Series. 1565:012098
The results of high temperature steam oxidation tests of cladding specimens made of VCPM at nominal test temperature of 1200 °C and exposure duration of up to 8.5 hours at GASPAR facility are presented. The experimental data were obtained by the ste
Publikováno v:
Atomic Energy. 117:161-168
A procedure is developed for performing on the PARAMETR stand integrated tests on VVER fuel-element simulators under conditions of the first stage of LOCA. The computational and methodological underpinnings of the experiments make it possible to cond
Autor:
Yu. A. Kuzma-Kichta, S. S. Bazyuk, D. M. Soldatkin, N. Ya. Parshin, E. B. Popov, D. N. Ignat’ev
Publikováno v:
Thermal Engineering. 60:323-330
A balance procedure is proposed for estimating the main parameters characterizing the process of model fuel assemblies reflooding of a VVER reactor made on different scales under the conditions of a design basis accident by subjecting them to bottom
Autor:
V. B. Usachev, P. P. Oleinikov, D. N. Ignatiev, D. M. Soldatkin, S. V. Priimak, A. N. Konotopov
Publikováno v:
Atomic Energy. 110:160-165
The objective of this work is to develop a computational-experimental method of determining the systematic error in measurements of the temperature of cooled fuel-element cladding using a thermocouple secured along the generatrix of the cladding. A m
Autor:
N. Ya. Parshin, A A Mokrushin, Yu A Kuzma-Kichta, D S Kiselev, E. B. Popov, D. M. Soldatkin, S. S. Bazyuk, I A Deryabin
Publikováno v:
Journal of Physics: Conference Series. 891:012180
The high-temperature oxidation tests were carried out for the regular fuel rod claddings specimens made of sponge-based zirconium alloy (E110G) and for the accident tolerant fuel (ATF) ones – pure vacuum melted molybdenum (VCPM) and niobium alloy (
Publikováno v:
AIP Conference Proceedings.
During the experiments simulating NPR (nuclear power reactor) accidents with a coolant loss fuel elements behavior in a steam-hydrogen medium was studied at the temperature changed with the rate from 1 to 100K/s within the range of 300÷1500 °C. Ind
Autor:
S S Bazyuk, I A Deryabin, D S Kiselev, Yu A Kuzma-Kichta, A A Mokrushin, N Ya Parshin, E B Popov, D M Soldatkin
Publikováno v:
Journal of Physics: Conference Series; Nov2017, Vol. 891 Issue 1, p1-1, 1p