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Moscow, Russia

Beznosov A.V.,Nizhny Novgorod State Technical University | Bokova T.A.,Nizhny Novgorod State Technical University | Antonenkov M.A.,Nizhny Novgorod State Technical University | Makhov K.A.,Nizhny Novgorod State Technical University | And 3 more authors.
Russian Engineering Research | Year: 2010

The wear of frictional steel and cast-iron surfaces in high-temperature (400-550°C) liquid-metal coolants in BREST and SVBR nuclear-power units is studied experimentally. It is shown that long life of the surfaces in reactor operation may be ensured by applying and maintaining protective oxide coatings. © 2010 Allerton Press, Inc. Source


Drozdov Y.N.,RAS Blagonravov Institute of Mechanical Engineering | Tananov M.A.,RAS Blagonravov Institute of Mechanical Engineering | Osipova E.P.,RAS Blagonravov Institute of Mechanical Engineering | Makarov V.V.,OAO OKB Gidropress | And 2 more authors.
Russian Engineering Research | Year: 2012

Intrinsic and forced vibrations of a reactor pile in standing water and in coolant flux are investigated. The eigenfrequencies and damping factors of the intrinsic vibrations and the parameters of forced vibrations of the fuel rods are determined. The influence of the auxiliary spacers on fuel-rod vibrations is discussed. © 2012 Allerton Press, Inc. Source


Drozdov Y.N.,RAS Blagonravov Institute of Mechanical Engineering | Osipova E.P.,RAS Blagonravov Institute of Mechanical Engineering | Nazarova T.I.,RAS Blagonravov Institute of Mechanical Engineering | Makarov V.V.,OAO OKB Gidropress | And 3 more authors.
Russian Engineering Research | Year: 2011

Fuel-rod casings and spacing cells are subjected to frictional tests, with variation in the technological and operational factors. © 2011 Allerton Press, Inc. Source


Drozdov Y.N.,RAS Blagonravov Institute of Mechanical Engineering | Osipova E.P.,RAS Blagonravov Institute of Mechanical Engineering | Puchkov V.N.,RAS Blagonravov Institute of Mechanical Engineering | Makarov V.V.,OAO OKB Gidropress | And 2 more authors.
Russian Engineering Research | Year: 2011

The wear resistance of fuel assemblies in the VVER-440 water-moderated reactor is investigated, with small fuel-rod diameter. The experimental apparatus, the model of the fuel rods, and the similarity conditions are described; the possibility of applying the experimental results to regular fuel rods is noted. © 2011 Allerton Press, Inc. Source


Drozdov Y.N.,RAS Blagonravov Institute of Mechanical Engineering | Tananov M.A.,RAS Blagonravov Institute of Mechanical Engineering | Osipova E.P.,RAS Blagonravov Institute of Mechanical Engineering | Nazarova T.I.,RAS Blagonravov Institute of Mechanical Engineering | And 3 more authors.
Russian Engineering Research | Year: 2012

Seismic tests of full-scale mockups of fuel assemblies from the VVER-1000 reactor permit the determination of the transfer characteristics between the stimulus (acceleration of the supports) and the response of the fuel assemblies. No resonant responses of the fuel assemblies to seismic loads are observed. © 2012 Allerton Press, Inc. Source

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