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E.V. Chertopyatov
E.V. Chertopyatov
Cladding (metalworking)
Materials science
Nuclear engineering
Irradiation
Post Irradiation Examination
3
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1
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Results of post-irradiation examinations of the sponge-based E110 opt. alloy operated as fuel cladding material in alternative TVSA-ALPHA up to attaining a burnup of 42 MW·day/kg U to establish the experimental databank in support of Russian fuel licensing for PWR plants
2019
Yu. D. Goncharenko
S.G. Eremin
E.V. Chertopyatov
Alexander Obukhov
T.M. Bulanova
G. V. Shishalova
A. Yu. Shevyakov
S. A. Bekrenev
V. V. Novikov
V. A. Markelov
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Change of the mechanical properties of cladding during thermal tests simulating the routine of fuel element dry storage of VVER-1000 reactor
2018
A.O. Mazaev
G. P. Kobylyansky
E. A. Zvir
E.V. Chertopyatov
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