Results 31 to 40 of about 1,019,583 (175)

Computational benchmark for fuel assembly of VVER-1000 using the Monte Carlo Serpent code [PDF]

Nuclear Technology and Radiation Protection, 2018
The use of a new Monte Carlo Serpent code for the calculation of water-cooled reactors is presented and a calculation scheme of the fuel assembly for VVER-1000 reactors developed.
Galchenko Vitaliy V., Shlapak Ihor, Gulik Volodymyr   +2 more
doaj   +1 more source

Investigation of the small break conditions in the primary circuit of a VVER-1000 reactor* [PDF]

Nuclear Energy and Technology, 2019
Modes with violation of the reactor plant cooling conditions on the primary circuit side of a VVER reactor were simulated using the TRAC-PD2 and Open FOAM thermohydraulic codes (TRAC-PD2 1981, OpenFOAM User Guide Version 1.6. 2009, OpenFOAM Programmer’s Guide Version 1.6.
Belozerov,Vladimir, Zhuk,Mikhail, Terekhova,Anna   +2 more
openaire   +3 more sources

Analysis of VVER-1000 mock-up criticality experiments with nuclear data library ENDF/B-VIII.0 and Monte Carlo code MCS

Nuclear Engineering and Technology, 2021
The criticality analysis of VVER-1000 mock-up benchmark experiments from the LR-0 research reactor operated by the Research Center Rez in the Czech Republic has been conducted with the MCS Monte Carlo code developed at the Computational Reactor Physics ...
Fathurrahman Setiawan, Matthieu Lemaire, Deokjung Lee   +2 more
doaj   +1 more source

Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode

Alexandria Engineering Journal, 2018
Removing the residual heat from a nuclear reactor is an important safety aspect of thermal hydraulic analysis. In this study, a typical VVER-1000 reactor residual heat removal system has been evaluated using RELAP5 thermal hydraulic loop code during cool-
Z. Tabadar, M. Jabbari, M. Khaleghi, M. Hashemi-Tilehnoee   +3 more
doaj   +1 more source

Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

EPJ Web of Conferences, 2016
A set of benchmark experiments was carried out in the full scale VVER-1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation ...
Košťál Michal, Milčák Ján, Cvachovec František, Jánský Bohumil, Rypar Vojtěch, Juříček Vlastimil, Novák Evžen, Egorov Alexander, Zaritskiy and Sergey   +8 more
doaj   +1 more source

Formation of proliferation-resistant nuclear fuel supplies based on reprocessed uranium for Russian nuclear technologies recipient countries

Nuclear Energy and Technology, 2015
The paper presents different strategies for the conversion of VVER-1000 reactors to reprocessed uranium fuel for estimating the time required to form a proliferation-resistant VVER-1000 fuel load based on uranium extracted from spent fuel of reactors of ...
M.I. Fedorov, A.I. Dyachenko, N.A. Balagurov, V.V. Artisyuk   +3 more
doaj   +1 more source

Radiological Safety Analysis for a Hypothetical Accident of a Generic VVER‐1000 Nuclear Power Plant

Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020
Atmospheric dispersion modelling and radiological safety analysis have been performed for a postulated accident scenario of a generic VVER‐1000 nuclear power plant using the HotSpot Health Physics code. The total effective dose equivalent (TEDE), the respiratory time‐integrated air concentration, and the ground deposition concentration are calculated ...
K. Gyamfi, S. A. Birikorang, E. Ampomah-Amoako, J. J. Fletcher, Leon Cizelj   +4 more
wiley   +1 more source

The Choice of Nuclear Energy for Ghana as a Result of Development of Its Energy Production

Journal of Energy, Volume 2020, Issue 1, 2020., 2020
Ghana thought of nuclear energy early in the 1960s but has not been able to realize this dream of generating electricity from nuclear power. Ghana’s electricity generation dates back to the Gold Coast era where the main source of electricity supply (isolated diesel generators) was owned by industrial establishments, municipalities, and other ...
Kwame Gyamfi, Sylvester Attakorah Birikorang, Emmanuel Ampomah-Amoako, John Justice Fletcher, Bernard Osei, Ciro Aprea   +5 more
wiley   +1 more source

Assessment of the TiO2/water nanofluid effects on heat transfer characteristics in VVER-1000 nuclear reactor using CFD modeling

Nuclear Engineering and Technology, 2015
The most important advantage of nanoparticles is the increased thermal conductivity coefficient and convection heat transfer coefficient so that, as a result of using a 1.5% volume concentration of nanoparticles, the thermal conductivity coefficient ...
Seyed Mohammad Mousavizadeh, Gholam Reza Ansarifar, Mansour Talebi   +2 more
doaj   +1 more source

Modernized surveillance program of the VVER-1000 reactor pressure vessel metal of the Ukrainian NPP unit [PDF]

Ядерна фізика та енергетика
The surveillance program is an important source of information on the change in the properties of the metal of the water-water power reactor pressure vessel during operation.
O. V. Grytsenko, V. N. Bukanov, O. G. Vasylieva, V. L. Diemokhin, О. M. Pugach, V. M. Revka, O. V. Trygubenko, E. M. Chalyi, Yu. V. Chaikovskyi   +8 more
doaj   +1 more source