Melikhov O.I.,Electrogorsk Research and Engineering Center |
Elkin I.V.,RAS Research Center Kurchatov Institute |
Melikhov V.I.,Electrogorsk Research and Engineering Center |
Nikonov S.M.,Electrogorsk Research and Engineering Center |
And 4 more authors.
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2014
In 2012 on the large-scale thermalphysic PSB-VVER facility modelling of three different type accidents is executed: - Guillotine rupture of the pipeline on a reactor inlet; - A small leak from "the cold" pipeline; - Rupture of pressurizer surge line. In experiments work of passive safety systems of new projects of NPP with RU VVER in the conditions of loss of all sources of an alternating current was modelled. The purpose of experiments was research of influence of new passive safety systems on a temperature condition of a fuel cladding. On the basis of the received experimental data verification of the Russian system codes TRAP-KS, KORSAR/GP and SOCRAT is executed. In paper the basic results of researches are presented. Copyright © 2014 by ASME.
Petkevich P.,Experimental and Design Organization GIDROPRESS |
Abramov V.,Experimental and Design Organization GIDROPRESS |
Yuremenko V.,Experimental and Design Organization GIDROPRESS |
Piminov V.,Experimental and Design Organization GIDROPRESS |
And 2 more authors.
Nuclear Engineering and Design | Year: 2014
Transportation of the nuclear fuel containing objects is especially sensitive to accidental drops, as any event, affecting the fuel spacial arrangement, alters also neutron multiplication factor and can result in uncontrolled chain reaction. The latter is particularly important for nuclear fuel being immersed in water. Apart from that, fall can result in a mechanical damage of the fuel rods, which can cause environmental pollution by radionuclides. Final and intermediate fuel configurations during the accident depend on the impact velocity and the angle between falling object and the surface. Experiments cannot cover all the possible variants of drops, as it would result in their unacceptable prices. Therefore elaboration of the approaches to numerically simulate such kind of accidents is an essential step in the nuclear fuel transportation safety analysis and is the principal goal of the present research. Series of drop tests with fuel assemblies (FA) models of different complexity have been performed and numerically simulated with LS-Dyna software in order to proof the reliability of such kind of analysis. The paper contains description of the drop test experimental facility, some experimental results and their numerical simulation. It has been found that the finite element model of the FA and the material properties used for the simulation provide reliable predictions of the FA materials deformation and failure in case of accidental drops onto a rigid surface. © 2013 Elsevier B.V.
Podshibyakin M.A.,Experimental and Design Organization GIDROPRESS
7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010 | Year: 2010
I&C software verification should be realized with the application of the control object full-scope model (process model) including time-dependent design conditions. It is one of the most effective ways of the software errors exposure, and occasionally is single. It allows to verify simultaneously pure I&C algorithms and I&C software with interactions considered. It may be especially effective in case of computer-aided design application for I&C software automatic creation. The possibility of best-estimate thermalhydraulic computer code application for I&C verification and, especially, validation has been demonstrated. "Real time" problem may be solved by process model simplification and also by pure I&C software verification results comparison with I&C hardware and software validation results.