Collection De Nates Internes

collection de nates internes

EXECUTIVE SUMMARY : Alloy 600 has been used for the fabrication of steam generator tubes of many pressurized water nuclear reactors. In primary water, this alloy is sensitive to a stress corrosion cracking phenomenon (PWSCC). We have characterized by X-ray diffraction cold work near die surface of tubes from various manufacturers. In particular, the effects of sandblasting, abrasive band polishing and heat treatment at 7000C have been examined. The results of three types of accelerated corrosioo tests (tests on reverse U-bends, constant extension rate tests and constant load tests) have been analysed using this characterization of superficial cold work.