Initiation and propagation of stress-corrosion cracking of Alloy 600 in high-temperature water. [PWR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5494427

Bandy, R; van Rooyen, D

Results of stress-corrosion cracking data are presented for Inconel 600 steam-generator tubing. U-bend, constant-load, and slow extension-rate tests are included. Arrhenius plots are presented for failure times vs inverse temperature for crack initiation and propagation. Effect of applied load is expressed in terms of log-log curves for failure times vs stress, and variations in environment and cold work are included. Microstructure and composition of oxide films on Inconel 600 surfaces were examined after exposure to pure water at 365/sup 0/C, and stripping with the bromine-methanol method. Results are discussed in terms of transient creep, film rupture and a mass-transport-limited anodic process.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5494427
• Report Number(s): BNL-NUREG-33657; CONF-830845-7; ON: DE84000623
• Resource Relation: Conference: Environmental degradation of materials in nuclear power systems-water reactors, Myrtle Beach, SC, USA, 22 Aug 1983
• Country of Publication: United States
• Language: English

Related Subjects

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