Results 21 to 30 of about 648 (179)
Experience of using loose parts monitoring systems at Novovoronezh NPP [PDF]
Nuclear Energy and Technology, 2022 In VVER reactor plants, it is impossible to completely exclude the appearance of loose, loosely fixed and foreign objects in the main circulation circuit.
Alexey V. Voronov, Mikhail T. Slepov
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Fuel Performance Comparison of Uranium Nitride and Uranium Carbide in VVER-1200 using OpenMC [PDF]
MATEC Web of ConferencesNuclear power is a reliable and large-scale source of GHG-free electricity. This study asses the viability of ATF fuel of uranium nitride (UN) and uranium carbide (UC) as fuel for the VVER-1200 reactor.
Jamil Meekal, Ali Majid
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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. +2 more
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Estimation influence of boric acid drop entrainment to its accumulation in the VVER reactor in the case of accident [PDF]
Nuclear Energy and Technology, 2018 Process of boric acid mass transfer during accidents accompanied with rupture of circulation pipelines in VVER reactors of new generation equipped with passive safety systems are examined.
Andrej V. Morozov +5 more
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Rooppur Nuclear Power Plant: Current Status & Feasibility
Journal of Mechanical Engineering, 2018 In the present world, nuclear energy is a must need for various purposes. The main cause of nuclear energy is because of the increasing energy demand, which is not possible to provide by using convenient energy generation.
Sabhasachi Saha +4 more
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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 +3 more
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VVER-1000 reactor model using the Serpent 2 code for core power distribution calculation [PDF]
Ядерна фізика та енергетика, 2023 A VVER-1000 reactor model using the Monte Carlo Serpent 2 code for core power distribution calculation is presented. The core and zones located near to the core were modeled in detail, without simplification.
V. V. Ilkovych
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A methodology for CHF prediction in VVER rod bundles
Nuclear Engineering and Design, 2022 The critical heat flux (CHF) is an important thermal-hydraulic parameter that must be determined during the design of water-cooled reactors to ensure safety of operation. In this paper, a methodology is proposed to predict the CHF in VVER rod bundles. A whole-reactor model of VVER-1000 is implemented in RELAP-SCDAPSIM, and, based on the bundle-average ...
AbdulHameed, Mohamed +3 more
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Tolerant fuel for VVER reactors
Journal of Physics: Conference Series, 2020 Abstract The main factor of destruction of fuel rods in accidents with loss of coolant is associated with the vapor-zirconium reaction occurring between the fuel rod shell and the coolant (water). Improving the reliability of fuel cells can be obtained by modifying or replacing the fuel shell, materials that do not interact with the ...
A Z Alhmoud +3 more
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The problem of minimizing the radioactive leakage into the VVER circuit under normal conditions
Trudy Odesskogo Politehničeskogo Universiteta, 2017 According to the Strategic Energy Technologies plan, two priorities have been accepted by the European Commis-sion: develop and strengthen energy-efficient systems; increase safety in the use of nuclear energy.
Сергій Миколайович Пелих +3 more
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