Evaluation of the parameters of wear law for heat-exchange tube–spacer grid pair of steam generator of REST-OD-300 nuclear reactor plant operating in argon atmosphere


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Abstract

Data on the wear tests of the material of a heat exchange tube and a spacer grid of the steam generator of the BREST-OD-300 nuclear reactor plant performed at a high temperature in argon atmosphere are presented. A mathematical model of the wear process based on which the identification of the corresponding wear law is carried out has been proposed. The wear durability of the heat exchange tube has been evaluated.

About the authors

I. G. Goryacheva

Ishlinskii Institute for Problems in Mechanics

Author for correspondence.
Email: goryache@ipmnet.ru
Russian Federation, pr. Vernadskogo 101/1, Moscow, 119526

A. P. Goryachev

Moscow Engineering Physics Institute National Research Nuclear University

Email: goryache@ipmnet.ru
Russian Federation, Kashirskoe sh. 31, Moscow, 115409

V. V. Lemekhov

Dollezhal’ Research and Development Institute of Power Engineering

Email: goryache@ipmnet.ru
Russian Federation, ul. Malaya Krasnosel’skaya 2/8, Moscow, 107140

O. P. Arkhipov

Dollezhal’ Research and Development Institute of Power Engineering

Email: goryache@ipmnet.ru
Russian Federation, ul. Malaya Krasnosel’skaya 2/8, Moscow, 107140

V. V. Tarasov

Institute of Mechanics, Ural Branch

Email: goryache@ipmnet.ru
Russian Federation, ul. T. Baramzinoi 34, Izhevsk, 426067

V. F. Lys

Institute of Mechanics, Ural Branch

Email: goryache@ipmnet.ru
Russian Federation, ul. T. Baramzinoi 34, Izhevsk, 426067

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