FIELD: testing technology.
SUBSTANCE: in the method of predicting resource capacity of steel of reactor vessels the samples of vessel steel is exposed to flow of fast neutrons with high density to the radiation dose corresponding to the radiation dose of the real reactor vessel for the distant term exceeding their design lifetime. The shift of the critical brittle point is determined, dependent on exposure to which for the materials of the reactor vessels VVER-1000 with nickel content ≥1.5% the component is added dependent on differences in kinetics of accumulation of radiation-induced precipitates during irradiation under conditions of different density of fast neutron flow. The level of grain boundary segregations in non-irradiated samples is determined and extrapolation - for the distant term of operation of the reactor. The overall shift of the critical brittle point is determined, and the resource of the vessel is determined according to its value.
EFFECT: improvement of accuracy of predicting shift of the critical brittle point of materials.
2 dwg
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Authors
Dates
2014-11-27—Published
2013-06-11—Filed