Aleksandrov Research Technological Institute NITI

Krasnyy Bor, Russia

Aleksandrov Research Technological Institute NITI

Krasnyy Bor, Russia
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Gusev B.A.,Aleksandrov Research Technological Institute NITI | Semenov V.G.,Saint Petersburg State University | Panchuk V.V.,Saint Petersburg State University
Technical Physics | Year: 2016

We have reported on the results of a numerical simulation of high-gradient magnetic filtration of ultradisperse corrosion products from water coolants. These results have made it possible to establish optimal technical characteristics of high-gradient magnetic filters. The results have been used to develop test samples of high-gradient magnetic filters (HGMFs) with different magnetic systems to purify technological water media of atomic power plants from activated corrosion products. © 2016, Pleiades Publishing, Ltd.


Vasilenko V.A.,Aleksandrov Research Technological Institute NITI | Migrov Yu.A.,Aleksandrov Research Technological Institute NITI | Zasukha V.K.,Aleksandrov Research Technological Institute NITI | Efimov V.K.,Aleksandrov Research Technological Institute NITI | And 2 more authors.
Atomic Energy | Year: 2014

Pressing questions concerning experimental modeling of thermohydraulic processes in NPP containment are examined. Domestic and foreign stands are briefly reviewed. It is shown that the KMS large-scale stand is necessary in order to obtain preliminary experimental data on the three-dimensional thermohydraulic processes occurring inside NPP containment and to verify modern computational codes. © 2014 Springer Science+Business Media New York.


Vasilenko V.A.,Aleksandrov Research Technological Institute NITI | Migrov Yu.A.,Aleksandrov Research Technological Institute NITI | Zasukha V.K.,Aleksandrov Research Technological Institute NITI | Efimov V.K.,Aleksandrov Research Technological Institute NITI | And 2 more authors.
Atomic Energy | Year: 2014

The main technical characteristics of the KMS stand as a large-scale model for NPP containment with VVER are presented. It is shown that this stand can be used to study three-dimensional heat and mass transfer processes in the containment atmosphere and to test systems and equipment used in NPP with VVER under close to anticipated and unanticipated accident conditions. In the future, with appropriate development work and additions to the stand it will be possible to study the rate of removal of aerosol particles having different chemical properties, perfect new designs of catalytic hydrogen recombiners and test equipment with the limiting parameters of the containment atmosphere. © 2014 Springer Science+Business Media New York.


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.


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.


Zmitrodan A.A.,Aleksandrov Research Technological Institute NITI | Rakov V.T.,Aleksandrov Research Technological Institute NITI | Sarancha O.N.,Aleksandrov Research Technological Institute NITI | Kornev Yu.K.,Aleksandrov Research Technological Institute NITI
Atomic Energy | Year: 2012

The radiometric method is based on the use of tritium as a reference radionuclide, and the method of detecting nonvolatile radionuclides is based on determining the intensity of gamma-radiation from the charge of ion-exchange filters in the second loop. The radiometric method is based on the use of tritium as a reference radionuclide, and the method of detecting nonvolatile radionuclides is based on determining the intensity of gamma-radiation from the charge of ion-exchange filters in the second loop. The changes of the tritium activity were of the following character: after the steam-generating facility reached the turbo-generator regime and the steam generators were connected to the condensate-feed system, the presence of tritium was detected in the second-loop water in amounts 3-19 times greater than the lowest detectable level, after which during operation a tendency for the activity to decrease gradually to the lowest detectable level was observed.


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

During the commercial production of60Co at the Leningradskaya nuclear power plant by irradiation of59Co in special facilities loaded into a RBMK core, computational means are used to determining the cobalt activity in the irradiation facilities and to decide whether or not they should be extracted. The computational results of the cobalt activity as compared with the experimental data and the effect of refinements in the computational model on them are presented. © 2010 Springer Science+Business Media, Inc.


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.


Oleinik M.S.,Aleksandrov Research Technological Institute NITI | Epimakhov V.N.,Aleksandrov Research Technological Institute NITI | Pankina E.B.,Aleksandrov Research Technological Institute NITI
Atomic Energy | Year: 2010

The use of Cambrian clay from Leningrad oblast for cementing radioactive sludge deposits from natural water reservoirs is discussed. The addition of Cambrian clay impedes separation of the mixture of sludge with cement and decreases the leaching of 137Cs from the solidified products at least five-fold. © 2010 Springer Science+Business Media, Inc.


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.

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