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Vinogorov N.A.,Aleksandrov Research Technological Institute NITI
Atomic Energy | Year: 2010

The temperature effect of reactivity with extracted control rods in the reactor core were investigated. Measurements of the temperature coefficient with overcompensation of the rods provides information on the dependence of the temperature coefficient on the position of the rods. Overcompensation of the rods was performed while maintaining the coolant temperature constant. The change of the water volume fraction characterizes the change of the uranium-water ratio. At fixed temperature a correlation is observed between the relative change of the temperature coefficient and the water fractions in the core. The results also show a difference of the temperature coefficient in different states. Integration of the functions in the temperature range 50-298°C estimates the effect of reactivity as, 5.45% and -3.99%, respectively. Source


Vinogorov N.A.,Aleksandrov Research Technological Institute NITI | Martyushev D.A.,Aleksandrov Research Technological Institute NITI
Atomic Energy | Year: 2015

A method of measuring the subcriticality of a reactor, according to which the reactor is transferred from a critical into a subcritical state twice by moving control rods with different velocities V1 and V2, is substantiated. A correction to the indications of a reactivity meter for the spatial effect of reactivity is calculated according to detector signals which are recorded with each movement. The correction calculation does not require neutron-physical calculations. As an example this method is applied to water-moderated and -cooled reactors. © 2015, Springer Science+Business Media New York. Source


Vinogorov N.A.,Aleksandrov Research Technological Institute NITI
Atomic Energy | Year: 2013

The transient processes induced in a water-moderated and -cooled reactor by prolonged (several seconds) insertion of absorbing rods into the reactor are analyzed using experimental and computational data. The change in the neutron flux density in core regions, forming the detector signal, during the motion of the rods, and the subsequent change in the distribution of delayed-neutron sources are examined. The spatial effect of the reactivity is determined from the coefficient of nonuniformity of the neutron flux density. The conditions under which regression analysis can be used to determine the efficiency of the rods are discussed. © 2013 Springer Science+Business Media New York. Source


Bezlepkin V.V.,East European Leading Research and Design Institute for Power Technologies VNIPIET | Zatevakhin M.A.,East European Leading Research and Design Institute for Power Technologies VNIPIET | Krektunov O.P.,East European Leading Research and Design Institute for Power Technologies VNIPIET | Krylov Yu.V.,East European Leading Research and Design Institute for Power Technologies VNIPIET | And 5 more authors.
Atomic Energy | Year: 2014

The EUR-required passive system for protection against unanticipated accidents in nuclear reactors has been developed. This system and the computational results obtained using three-dimensional computer codes are described. The experimental data are compared with numerical experiments performed using three-dimensional hydrodynamic codes and the KUPOL-M lumped-parameter code. The experiments made it possible to refine the closure relations used in integral codes. © 2014 Springer Science+Business Media New York. Source


Artemov V.G.,Aleksandrov Research Technological Institute NITI | Elshin A.V.,Aleksandrov Research Technological Institute NITI | Ivanov A.S.,Aleksandrov Research Technological Institute NITI | Gorbunov E.K.,Leningradskaya Nuclear Power Plant | And 2 more authors.
Atomic Energy | Year: 2010

Commercial production of 60Co is being conducted at the Leningradskaya nuclear power plant by irradiating 59Co in special facilities loading into an RBMK core (in all four units). The computational means used to determine the activity of cobalt in the irradiation setups and to decide when to extract them are described. The particularities of the computational model used for the core, which takes account of the reloading of the fuel assemblies and irradiation setups during fuel burnup, are described. © 2010 Springer Science+Business Media, Inc. Source

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