Results 31 to 40 of about 3,636 (213)
Improving the accuracy of thermal power determination of VVER
Ядерна фізика та енергетика, 2019 In most algorithms for forming control signals, locks and protection of VVER, the value of the reactor’s thermal power (RTP) is used. This article is dedicated to the analysis of the problem of determining the RTP of VVER-1000.
V. I. Borysenko +2 more
doaj +1 more source
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 +2 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 +3 more
doaj +3 more sources
Automated system for control of VVER-1000 fuel properties considering fuel cladding damage parameter. [PDF]
Trudy Odesskogo Politehničeskogo Universiteta, 2018 An automated system for control of VVER-1000 reactor fuel properties considering fuel element cladding damage parameter, fuel burnup and axial offset has been proposed.
Pelykh S. +3 more
doaj +1 more source
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 +2 more
openaire +1 more source
VVER-1000 BENCHMARK INTERPRETATION WITH MONTE CARLO CODE MCS [PDF]
EPJ Web of Conferences, 2021 An interpretation of the NEA-1517/82 benchmark from the SINBAD shielding database has been conducted with the MCS Monte Carlo code developed at the Ulsan National Institute of Science and Technology (UNIST) and the ENDF/B-VII.1 nuclear data library.
Setiawan Fathurrahman +4 more
doaj +1 more source
In-Vessel Melt Retention (IVMR) Analysis of a VVER-1000 NPP [PDF]
, 2016 As part of the outcome of the EU “Stress Tests” in 2012, several areas for further research in the field of Severe Accident Management have been identified for different types of NPPs.
BAJARD Sophie +21 more
core +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 +4 more
wiley +1 more source
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 +8 more
doaj +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 +5 more
wiley +1 more source