Mechanisms of stress corrosion cracking and intergranular attack in Alloy 600 in high temperature caustic and pure water

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6216507

Bandy, R; van Rooyen, D

In recent years, several studies have been conducted on the intergranular stress corrosion cracking (SCC) and intergranular attack (IGA) of Alloy 600. A combination of SCC and IGA has been observed in Alloy 600 tubing on the hot leg of some operating steam generators in pressurized water reactor (PWR) nuclear power plants, and sodium hydroxide along with several other chemical species have been implicated in the tube degradations. SCC has been observed above and within the tube sheet, whereas IGA is generally localized within the tube sheet. Alloy 600 is also susceptible to SCC in pure and primary water. Various factors that influence SCC and IGA include metallurgical conditions of the alloy, concentrations of alkaline species, impurity content of the environment, temperature and stress. The mechanisms of these intergranular failures, however, are not well understood. Some of the possible mechanisms of the SCC and IGA in high temperature water and caustic are described in this paper.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6216507
• Report Number(s): BNL-NUREG-35520; CONF-8410208-1; ON: TI85005129
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALKALI METAL COMPOUNDS
ALLOYS
BOILERS
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
HYDROGEN COMPOUNDS
HYDROXIDES
INCONEL 600
INCONEL ALLOYS
INTERGRANULAR CORROSION
IRON ALLOYS
KINETICS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTION KINETICS
REACTORS
SODIUM COMPOUNDS
SODIUM HYDROXIDES
STEAM GENERATORS
STRESS CORROSION
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS