Determination of the Containment Lifetime Characteristics as a Problem of Controlling the Life Cycle of NPP with VVER-1000


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Abstract

A systems approach to evaluating the service life of the reinforced, prestressed, concrete, containment shell of an NPP with VVER-1000 is examined. The main steps in evaluating the technical condition and remaining service life of its structural units are described. An additional 30-year period of operation of the containment shell of the No. 1 unit of the Kalininskaya NPP and the Nos. 2 and 3 units of the Balakovo NPP is determined on the basis of these investigations.

About the authors

V. V. Potapov

All-Russia Research Institute for Operation of Nuclear Power Plants (VNIIAES)

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

A. M. Loginov

All-Russia Research Institute for Operation of Nuclear Power Plants (VNIIAES)

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

V. A. Il’in

All-Russia Research Institute for Operation of Nuclear Power Plants (VNIIAES)

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

V. G. Kolomiets

All-Russia Research Institute for Operation of Nuclear Power Plants (VNIIAES)

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

A. P. Pustovgar

Moscow State University of Civil Engineering (MGSU)

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

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