The results of a study of the radiation resistance of the alloy SAV-1, which is the primary structural material of VVR-M reactor, are presented. During 2008–2010, reactor tests and post-reactor materials’ studies were performed on samples irradiated to fluence ~3.5·1022 cm–2 (E > 0.8 MeV) in the SM and to 4.45·1021 cm–2 in the VVR-M reactors. Data are presented on the erosion and structural characteristics of the samples and the computed and experimental changes in the silicon content in the alloy. The mechanical characteristics of the samples were studied. The stress–strain state of the support lattice of VVR-M and the horizontal channel GEK-4 as well as their resistance to brittle fracture were calculated on the basis of the mechanical characteristics obtained for the alloy. The data obtained are now used as the basis for validating service life extension for VVR-M.
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Translated from Atomnaya Énergiya, Vol. 118, No. 5, pp. 274–278, May, 2015.
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Konoplev, K.A., Fridman, S.R., Orlov, S.P. et al. Investigation of the Radiation Resistance of the Alloy SAV-1 Irradiated to Fluence ~3.5·1022 cm−2 (E > 0.8·MeV). At Energy 118, 341–345 (2015). https://doi.org/10.1007/s10512-015-0004-8
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DOI: https://doi.org/10.1007/s10512-015-0004-8