Abstract
Abstract Alloy 690 is used to replace Alloy 600 for the fabrication of tubes for steam generators of french pressurized water nuclear reactors. In order to reduce the dispersion in tensile properties observed for the first Alloy 690 industrial tubes, and which had already been noticed for Alloy 600, a joint research programme has been carried out by Electricite de France (Departement Etude des Materiaux) and Valinox Montbard. The dispersion in the tensile properties of the first industrial Alloy 690 tubes for PWR steam generators arises from two main factors: • - a grain size dispersion which is in particular controlled by the carbon content and by the final heat treatment, • - differences in the degree of strain hardening induced by the straightening process with rollers. An improvement of the fabrication processes which have an influence on these two factors has allowed to reduce considerably the dispersion of the tensile properties of the more recent series of tubes.
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