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


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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.

作者简介

V. Potapov

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

A. Loginov

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

V. Il’in

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

V. Kolomiets

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

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

A. Pustovgar

Moscow State University of Civil Engineering (MGSU)

Email: j-atomicenergy@yandex.ru
俄罗斯联邦, Moscow

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