Investigation of friction joints working in nuclear plant with heat transfer medium consist of heavy high temperature liquid metal

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Abstract

The experimental equipment developed for the decision of tribological problems, arising at use of friction joints in the environment of heavy liquid metals is submitted as heat-transfer medium for contours of nuclear power installations. For researches of fretting-corrosion of heat release pipes in contact with spacer grid cell the installation modelling a fretting process in the contacts with the purpose of a substantiation of vibration strength of a steam generator of a reactor on fast neutrons with the lead heat transfer medium is created. Experimental installation for research and resource tests of cylindrical involute gearings and the sliding bearings working in reactors on fast neutrons in the environment of the lead heat transfer is described. Experimental samples of circulating pumps for reactor installations, intended for research of wear process characteristics of steel and cast iron sliding support working in the environment of lead, eutectic alloys lead - bismuth and lead - lithium are developed.

About the authors

Yu. N. Drozdov

Mechanical Engineering Research Institute, Moscow

Author for correspondence.
Email: vest@ssau.ru
Russian Federation

A. V. Beznosov

Nizsegorodskii State Technical University by Name of R.E.Alekseev

Email: vest@ssau.ru
Russian Federation

V. V. Makarov

FSUE OKB “Gidropress”, Podolsk, Russia

Email: vest@ssau.ru
Russian Federation

V. N. Puchkov

Mechanical Engineering Research Institute, Moscow

Email: vest@ssau.ru
Russian Federation

M. A. Antonenkov

Nizsegorodskii State Technical University by Name of R.E.Alekseev

Email: vest@ssau.ru
Russian Federation

D. V. Kuznetsov

Nizsegorodskii State Technical University by Name of R.E.Alekseev

Email: vest@ssau.ru
Russian Federation

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