Results 1 to 10 of about 283 (140)
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 +2 more
doaj +3 more sources
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 +2 more
doaj +2 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 +5 more sources
Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code [PDF]
Nuclear Energy and Technology, 2023 The goal of this study is to perform neutronic calculations of the VVER-1000 MOX core computational benchmarks with an OpenMC code along with ENDF/B-VII.1 nuclear data library.
Md Imtiaj Hossain +3 more
doaj +3 more sources
Calculation of radiation fields in the VVER-1000 concrete biological shield using Monte Carlo code Serpent [PDF]
Ядерна фізика та енергетика, 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 the
O. M. Khotiaintseva +5 more
doaj +1 more source
Validation of the MCNP model of formation of the background wires current of the self-powered neutron detectors of VVER-1000 [PDF]
Ядерна фізика та енергетика, 2023 The article presents the results of the numerical simulation of the signal formation process of the background wires of self-powered neutron detectors (SPND) under the action of gamma radiation in the VVER-1000 core using MCNP code. The validation of the
V. I. Borysenko, V. V. Goranchuk
doaj +1 more source
Multiple usage of thorium-based fuel in a VVER-1000 reactor
Nuclear Energy and Technology, 2022 This paper considers the use of unconventional fuel in nuclear power reactors, using the example of a VVER-type unit, in order to find out the possibility of saving natural fissile uranium nuclei. Saving fissile uranium is one of the important tasks, the solution of which will give time for the development of a two-component nuclear power industry that
Kazansky,Yury +2 more
openaire +3 more sources
Evaluation of neutronic performance for the VVER-1000 reactor core with regenerated uranium-plutonium fuel [PDF]
Nuclear Energy and Technology, 2023 The possibility has been considered for the VVER-1000 reactor fuel loading to be formed based on regenerated fuel with the use of the spent fuel accumulated in reactors of the same type.
Viktor V. Semishin
doaj +3 more sources
Глобальная ядерная безопасность, 2023 The paper considers the efficiency and possibility of implementing into the operational practice of VVER-1000 power units the campaign extension mode at the sliding pressure of the second circuit.
A. S. Grachev +2 more
doaj +1 more source
Trudy Odesskogo Politehničeskogo Universiteta, 2019 The VVER reactor investigation is an important goal for Ukrainian nuclear energy. Different deterministic and stochastic codes are using for this purpose.
Володимир Іванович Гулік +3 more
doaj +3 more sources