Zobrazeno 1 - 10
of 10
pro vyhledávání: '"V. I. Gulik"'
Autor:
O. M. Khotiaintseva, O. R. Trofymenko, V. M. Khotiaintsev, A. V. Nosovskyi, S. E. Sholomytsky, V. I. Gulik
Publikováno v:
Âderna Fìzika ta Energetika, Vol 24, Iss 3, Pp 231-238 (2023)
To calculate radiation fields in the concrete biological shield (CBS) of the VVER-1000 reactor in this work, we have developed and applied the Monte Carlo code Serpent simulation framework based on the variance reduction technique. We have quantified
Externí odkaz:
https://doaj.org/article/d0683a3cf88348369917b8e1f6e2d6be
Publikováno v:
Âderna Fìzika ta Energetika, Vol 19, Iss 4, Pp 366-375 (2018)
Description of computation model for Kyoto University Critical Assembly (KUCA) developed with the help of Monte-Carlo Serpent code was presented in this paper. The simulation of criticality and subcriticality condi-tions for KUCA was carried out. The
Externí odkaz:
https://doaj.org/article/9ef42a82f2a7430ca07bdad8b67c9b51
Autor:
V. I. Gulik
Publikováno v:
Âderna Fìzika ta Energetika, Vol 19, Iss 3, Pp 284-292 (2018)
Calculation model developed by means of Monte Carlo code MCNP 4c for 60Со gamma-irradiation source is presented. The simulation of gamma-ray transport in the developed model was carried out. Gamma-ray absorbed doses for different dwell positions we
Externí odkaz:
https://doaj.org/article/edc1a32d927749349324500649cd03ce
Publikováno v:
Âderna Fìzika ta Energetika, Vol 18, Iss 3, Pp 267-275 (2017)
n this work, propagation of the stationary nuclear fission wave was simulated for series of fixed power values using Monte Carlo code Serpent. The wave moved in the axial direction in 5 m long cylindrical core of fast reactor with pure 238U raw fuel.
Externí odkaz:
https://doaj.org/article/0f47128b16bb457b881e90bc9be4a187
Autor:
V. I. Gulik
Publikováno v:
Âderna Fìzika ta Energetika, Vol 18, Iss 4, Pp 331-340 (2017)
Investigations aimed for the optimization of fuel compositions for two-zone subcritical reactor are considered. The study of inner fast zone for two-zone subcritical reactor with homogeneous fuel concerning the geometrical, material and economical ch
Externí odkaz:
https://doaj.org/article/588bc98ff9134c8580fbb60d8544df02
Publikováno v:
Âderna Fìzika ta Energetika, Vol 17, Iss 3, Pp 250-258 (2016)
The description of calculation scheme of fuel assembly for preparation of few-group characteristics is considered with help of Serpent code. This code uses the Monte-Carlo method and energy continuous microscopic data libraries. Serpent code is devot
Externí odkaz:
https://doaj.org/article/58b12f6bc6ae419a898b3a0b9d6918ac
Publikováno v:
Âderna Fìzika ta Energetika, Vol 13, Iss 3, Pp 266-275 (2012)
Neutron-physical modelings of two-zone subcritical reactor driven by high-intensity neutron generator are considered. The cascade principle in subcritical reactors, the use of which can hypothetically substantially amplify the neutron flux from the e
Externí odkaz:
https://doaj.org/article/bf734978d0c64dbe9c4f9b076ea51637
Publikováno v:
Âderna Fìzika ta Energetika, Vol 9, Iss 1(23), Pp 56-61 (2008)
At present, the conception of design and construction of new research reactor and scientific nuclear centre in Ukraine is developed [1]. In this conception the construction of the pool type reactor with heat power 20 - 30 MW and with neutron flux in
Externí odkaz:
https://doaj.org/article/565a9b7d9bc2434297cb21fff6b40043
Autor:
V. I. Gulik, V. M. Pavlovych
Publikováno v:
Nuclear Power and the Environment. 13:6-16
Autor:
B. E. Ermakov, V. I. Gulik
Publikováno v:
Soviet Applied Mechanics. 16:149-153