Results 111 to 120 of about 302 (158)
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COMPUTER SIMULATION OF THERMOPHYSICAL PROCESSES IN THE VVER-1000 NUCLEAR REACTOR
Bulletin D. Serikbayev of EKTU, 2023The priority use of water-water reactors in the nuclear power industry is due to their advantages. Water is ideally suited as a moderator and refrigerant, providing compactness, high power and simple reactor design. Water-water reactors have high resistance and self-regulation due to the negative temperature
N. Aitbek +3 more
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NEUTRON-PHYSICAL CALCULATION OF THE VVER-1000 ON MOX-FUELED REACTOR
Energy Systems, 2023The use of mixed uranium-plutonium fuel in thermal reactors makes it possible to effectively use highly toxic weapons-grade plutonium for peaceful purposes. The world's reserves of such plutoni-um are a serious problem. The use of this fuel in thermal reactors significantly reduces the amount of enriched uranium needed, as well as to dispose of ...
Mikle Egorov, Alexander Blinnikov
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Application of global optimization to VVER-1000 reactor diagnostics
Progress in Nuclear Energy, 2003Problems of reactor equipment diagnostics are formulated as inverse eigenvalue problems. Numerical methods of solving the inverse problems are presented. Incompleteness of spectral data results in the error function being non-convex. As the function has numerous local minima, it is necessary to use global optimization methods.
V.G. Kinelev, P.M. Shkapov, V.D. Sulimov
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Calculation with MCNP of capture photon flux in VVER-1000 experimental reactor
Radiation Protection Dosimetry, 2005The aim of this study is to obtain by Monte Carlo method the high energy photon flux due to neutron capture in the internals and vessel layers of the experimental reactor LR-0 located in REZ, Czech Republic, and loaded with VVER-1000 fuel. The calclated neutron, photon and photon to neutron flux ratio are compared with experimental measurements ...
Candan, Töre, Pedro, Ortego
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Equilibrium thorium fuel loading in VVER-1000 reactor
Proceedings of the 2014 15th International Scientific Conference on Electric Power Engineering (EPE), 2014Thorium can be utilized in Pressurized Water Reactors (PWR) as ThO 2 fuel matrix supported by fissile materials. In this analysis, VVER-1000 reactor was taken as a representative of the PWR reactor group. The thorium fuel matrix was mixed with fissile material in form of pure 233U, enriched uranium (19.7 % enrichment) and Reactor-Grade plutonium ...
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CFD Simulation of Slug Mixing in VVER-1000 Reactor
Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 2006Recently, the safety analyses of VVER and PWR reactors have dealt with the possibility of reactivity-induced accidents related to the penetration of a water slug with low boron concentration into the reactor core. Loop seals at the reactor coolant pump (RCP) suction are the most likely places for the formation of these slugs.
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Simulation of the Flow Rotation and Mixing in the Downcomer of a VVER-1000 Reactor
Nuclear Technology, 2007Flow rotation and mixing in a WER-1000 reactor is investigated using two system codes with three-dimensional fluid-dynamics modeling capabilities (RELAP5-3D and TRACE) and a computational fluid-dynamics (CFD) code (FLUENT). Coarse-mesh models were developed for the system codes, and their applicability is evaluated using the test data as well as the ...
Emilian Popov +3 more
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Study of in-vessel melt retention for VVER-1000/v320 reactor
Nuclear Engineering and Design, 2016Abstract This study aims to assess the applicability of the in-vessel melt retention (IVMR) strategy with external vessel water cooling to the reactors of VVER-1000/v320 type. IVMR strategy is one of the feasible solutions to mitigate reactor vessel failure and further fission products release to the containment and to the environment outside.
Gencheva, R. +4 more
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Full-core reactor physics analysis for accident tolerant cladding in a VVER-1000 reactor
Annals of Nuclear Energy, 2021Abstract Advanced accident tolerant cladding materials have brought up the potential to delay the deleterious consequences of loos of coolant accidents related to slowing down hydrogen formation from reaction of zirconium with steam in order to minimize the additional heat generation and improve fuel and cladding retention of fission products.
O. Safarzadeh, M. Qarani-tamai
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Examination of VVER-1000 Reactor Pressure Vessel Head
2006This article presents examination VVER-1000 Reactor Pressure Vessel Head (RPVH). The scope of this examination includes the following: visual examination of RPVH interior as well as inside surface of penetration tube ; ultrasound examination of penetration tube from inner side and examination of J-weld area ; eddy current examination of inside surface ...
Pajnić, Mladen, Novosel, Dino
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