Determination of the Containment Lifetime Characteristics as a Problem of Controlling the Life Cycle of NPP with VVER-1000
- Authors: Potapov V.V.1, Loginov A.M.1, Il’in V.A.1, Kolomiets V.G.1, Pustovgar A.P.2
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Affiliations:
- All-Russia Research Institute for Operation of Nuclear Power Plants (VNIIAES)
- Moscow State University of Civil Engineering (MGSU)
- Issue: Vol 119, No 6 (2016)
- Pages: 380-383
- Section: Article
- URL: https://journal-vniispk.ru/1063-4258/article/view/248009
- DOI: https://doi.org/10.1007/s10512-016-0077-z
- ID: 248009
Cite item
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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