Computational and Experimental Validation of the Serviceability of RBMK Core Elements Under Graphite Stack Distortion Conditions


Cite item

Full Text

Open Access Open Access
Restricted Access Access granted
Restricted Access Subscription Access

Abstract

Computational and experimental validation of the serviceability of zirconium channels in the reactor core according to strength criteria was conducted in order to ensure safe operation of the RBMK reactor facility under graphite stack deformation conditions. A complex of computational and experimental studies confirmed that the requirements of the operative federal norms and regulations for objects using nuclear power are met

About the authors

S. V. Evropin

Dollezhal Research and Development Institute of Power Engineering (NIKIET)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

A. P. Rakhmanov

Dollezhal Research and Development Institute of Power Engineering (NIKIET)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

E. V. Churakova

Dollezhal Research and Development Institute of Power Engineering (NIKIET)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

I. M. Baranov

Dollezhal Research and Development Institute of Power Engineering (NIKIET)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

S. M. Usov

Dollezhal Research and Development Institute of Power Engineering (NIKIET)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

Supplementary files

Supplementary Files
Action
1. JATS XML

Copyright (c) 2018 Springer Science+Business Media, LLC, part of Springer Nature