Published November 1993
| Version v1
Journal article
Effects of carbides on susceptibility of alloy 600 to stress corrosion cracking in high-temperature water
- 1. Ohio State Univ., Columbus, OH (United States). Fontana Corrosion Center
Description
The electrochemical behavior of sensitized, carburized, and mill-annealed alloy 600 (UNS N06600) was studied in hydrogenated, aerated, and high-temperature (250 to 350 C) dilute aqueous solutions. In high-temperature water at high anodic potentials, the current density (DC) from carbide dissolution was higher than DC from matrix dissolution. In oxidizing environments, intergranular stress corrosion cracking propagated in alloy 600 by dissolution of continuous or semicontinuous carbides at the grain boundary, in sensitized and non-sensitized materials. These studies have been conducted in environments similar to those in the steam generators of pressurized water reactors (PWR) in nuclear power plants
Additional details
Publishing Information
- Journal Title
- Corrosion (Houston)
- Journal Volume
- 49
- Journal Issue
- 11
- Journal Page Range
- p. 867-876.
- ISSN
- 0010-9312
- CODEN
- CORRAK
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25035885
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CARBIDES; CORROSION RESISTANT ALLOYS; CRACK PROPAGATION; CURRENT DENSITY; INCONEL 600; INTERGRANULAR CORROSION; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; PWR TYPE REACTORS; STEAM GENERATORS; STRESS CORROSION
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; BOILERS; CARBON COMPOUNDS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; POWER REACTORS; REACTORS; THERMAL REACTORS; TITANIUM ADDITIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS