Results 31 to 40 of about 186 (119)
Analysis of the influence of nuclear fuel burnup on the 16N formation rate in the primary coolant of the WWER-1000 reactor [PDF]
Ядерна фізика та енергетика, 2021 The developed model of the WWER-1000 reactor using MCNP6.2 (Monte Carlo N-Particle Transport Code) includes the detailed core taking into account the design of the fuel assemblies, as well as the baffle, the lower plenum, the fuel support columns, the ...
Yu. Fylonych +3 more
doaj +1 more source
Brittle Fracture Probabilistic Assessment of WWER-1000 RPVs
Volume 3: Design and Analysis, 2014 This paper presents a methodology for brittle fracture probability assessment of WWER-1000 RPVs subjected to PTS. The main attention of the study is focused on the definition of the stochastic input data: fracture toughness, CTB, size and shape of the defects. Fracture toughness of RPV metal in the initial state is determined, separately
Igor Orynyak +4 more
openaire +2 more sources
International Standard Problems and Small Break Loss‐of‐Coolant Accident (SBLOCA)
Science and Technology of Nuclear Installations, Volume 2008, Issue 1, 2008., 2008 Best‐estimate thermal‐hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. Evaluation of the capabilities and the performance of these codes can be accomplished by comparing the code predictions with measured experimental data obtained on different test ...
N. Aksan, Cesare Frepoli
wiley +1 more source
Human reliability analysis in low power and shut-down probabilistic safety assessment: Outcomes of an international initiative [PDF]
Nuclear Technology and Radiation Protection, 2012 Since the beginning of the nuclear power generation, human performance has been a very important factor in all phases of the plant lifecycle: design, commissioning, operation, maintenance, surveillance, modification, and decommissioning.
Manna Giustino +2 more
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Глобальная ядерная безопасность, 2022 This paper presents the results of the influence of reactivity on fuel temperature distribution for the neutron-physical characteristics of WWER 1000-1200 cores, which in turn affects the parameters of Xenon oscillation.
R. T. Al Malkawi, L. J. Zadan
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An automated boron management system for WWER-1000 nuclear reactors
Trudy Odesskogo Politehničeskogo Universiteta, 2014 The article is devoted to the problem of creating a system of automated control with boron regulation for reactor WWER-1000 series. Using the boron regulation to control WWER-1000 allows to extend its maximum output operation period, ensuring the ...
Таїсія Олександрівна Цисельська +1 more
doaj +4 more sources
WWER-1000 core loading characteristic influence on irradiation conditions of surveillance specimens and reactor pressure vessel [PDF]
Ядерна фізика та енергетика, 2009 Irradiation conditions of WWER-1000 surveillance specimens and reactor pressure vessel are comparative analyzed for various core loadings. It is proved that the fluences onto specimens don't correlate with ones onto pressure vessel.
V. N. Bukanov +4 more
doaj
Determination of Stiffness Characteristics for WWER-1000 Support Components
Nuclear and Radiation Safety, 2019 Available approaches to computer justification of safe operation of reactor support components (RSC) are generally presented in the reports justifying RSC lifetime extension at Ukrainian NPPs. The experience of performing such calculations and analyzing the results indicates that there are issues to be improved.
V. Dubkovsky +3 more
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Simulation modeling of processes in the WWER-1000 reactor with power control by absorbing rods
Вісник Національного технічного університету "ХПÌ": Системний аналіз, управління та інформаційні технології, 2017 Mathematical models of WWER-1000 nuclear reactor of V-320 series are presented in the form of systems of differential equations in relative state variables.
Валерий Петрович Северин +2 more
doaj +1 more source
HEAT EXCHANGE CONDITIONS IN THE DRY STORAGE CONTAINER FOR SPENT NUCLEAR FUEL OF POWER REACTORS
Elektrotehnìka ta Elektroenergetika, 2018 Purpose. The safety substantiation of the spent nuclear fuel of power reactors WWER-1000 of Zaporizhska NPP dry storage facility operation by carrying out of numerical study of the thermal processes inside dry storage container. Methodology. Mathematical
S.V. Alyokhina
doaj +1 more source