Results 41 to 50 of about 675,221 (193)

Selection of a turbulence model to calculate the temperature profile near the surface of VVER-1000 fuel assemblies in the NPP spent fuel pool [PDF]

Nuclear Energy and Technology, 2021
The paper considers the problem of selecting a turbulence model to simulate natural convection near the surface of a VVER-1000 fuel assembly unloaded from the reactor by computational fluid dynamics (CFD simulation) methods.
Aleksandra V. Voronina, Sergey V. Pavlov
doaj   +3 more sources

Investigation of the impact of steady-state VVER-1000 (1200) core characteristics on the reactor stability with respect to xenon oscillations [PDF]

Nuclear Energy and Technology, 2020
The article presents a method for obtaining an analytical expression for the criterion of stability of a VVER-1000 (1200) reactor with respect to xenon oscillations of the local power in the core, containing an explicit dependence of the criterion ratio ...
Rashdan Talal Al Malkawi, Sergey B. Vygovsky, Osama Wasef Batayneh   +2 more
doaj   +3 more sources

Safety analyses of reactor VVER 1000

Energy Procedia, 2017
Abstract Department of Electrical Power Engineering, Faculty of Electrical Engineering and Communication, Brno University of Technology (BUT) is participating in research of safety analyses of nuclear power plants, especially nuclear power plants with VVER 1000 reactors.
Jitka Vojackova, Filip Novotny, Karel Katovsky   +2 more
openaire   +1 more source

LBLOCA accident investigation using TRACE code in a VVER-1000 reactor [PDF]

مجله علوم و فنون هسته‌ای, 2020
The loss of coolant accident is due to the reduction of the coolant fluid volume in the first circuit. The direct cause of this accident is the mechanical failure or fatigue in the material of the first circuit components during the power plant operation.
S. Ekbatani-Amlashi, O. Safarzadeh, A.S. Shirani   +2 more
doaj   +1 more source

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

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

Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code [PDF]

Nuclear Energy and Technology, 2022
A handful of computational benchmarks that incorporate VVER-1000 assemblies having low enriched uranium (LEU) and the mixed oxide (MOX) fuel have been put forward by many experts across the world from the Nuclear Energy Agency.
Md. Imtiaj Hossain, Yasmin Akter, Mehraz Zaman Fardin, Abdus Sattar Mollah   +3 more
doaj   +3 more sources

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

Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

EPJ Web of Conferences, 2016
Usually the synthesis of two-dimensional and one-dimensional discrete ordinate calculations is used to evaluate neutron fluence on VVER-1000 reactor pressure vessel (RPV) for prognosis of radiation embrittlement.
Dzhalandinov A., Tsofin V., Kochkin V., Panferov P., Timofeev A., Reshetnikov A., Makhotin D., Erak D., Voloschenko A.   +8 more
doaj   +1 more source