FIELD: mechanical engineering. SUBSTANCE: invention, in particular, relates to nuclear engineering and can be used for eliminating tendency to intercrystalline corrosion cracking in corrosive medium (reactor water). For units of structures operating under high-stress conditions, dispersion-hardening, corrosion-immune alloys are used preliminarily sensitized by heat treatment. For alloys operating under stress conditions resulting in elastic deformation of alloy, threshold stress exists independent of alloy sensitizing degree. On the contrary, threshold stress depends on alloy sensitizing degree if stress conditions cause plastic deformation of alloy. To prevent tendency to intercrystalline cracking in steels, invention, on the basis of diagram of alloy sensitizing-stress state, proposes use of relationship of sensitizing degree to threshold stress level and standardization, according to this diagram, of stress value and alloy sensitizing level. EFFECT: increased corrosion resistance of steel. 1 dwg, 3 tbl
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Authors
Dates
1997-08-20—Published
1993-11-29—Filed