Degradation of steam generator tubing and components by operation of pressurized-water reactors

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6887545

Weeks, J R; Czajkowski, C J

Experience in operating pressurized water reactors (PWR) has shown a number of materials degradation processes to have occurred in their steam generators. These include stress corrosion cracking (SCC), intergranular attack, generalized dissolution, and pitting attack on steam generator tubes; mechanical damage to steam generator tubes; extensive corrosion of tubing support plates (denting); and cracking of feedwater lines and steam generator vessels. The current status of the understanding of the causes of each of these phenomena is reviewed with emphasis on their possible significance to reactor safety and directions the nuclear industry and the NRC should be taking to reduce the rate of degradation of steam generator components.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6887545
• Report Number(s): BNL-NUREG-31864; CONF-820876-2; ON: DE83003720
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CORROSION
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
MATERIALS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEAM GENERATORS
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS