Susceptibility of unirradiated recrystallized Zircaloy-4 tubing to stress corrosion cracking (LWBR Development Program)

Technical Report · Thu Dec 01 04:00:00 EST 1977

DOI:https://doi.org/10.2172/5192610· OSTI ID:5192610

Polan, N. W.; Tucker, R. P.

Stress corrosion cracking (SCC) in unirradiated recrystallized Zircaloy-4 internally pressurized tubing specimens in atmospheres containing iodine vapor, cesium, or combinations of iodine and cesium is evaluated experimentally in terms of the effects of internal surface flaw morphology, iodine and cesium concentrations, tubing hydrogen content, test temperature, and test atmosphere water vapor content on the time to failure. The iodine vapor SCC data are analyzed in the framework of a fracture mechanics model. Expressions are developed which relate the iodine SCC threshold stress and lifetime for stresses above threshold to temperature, iodine concentration, and surface flaw geometry.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, Pa. (USA)
• DOE Contract Number: EY-76-C-11-0014
• OSTI ID: 5192610
• Report Number(s): WAPD-TM-1313
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
ALKALI METALS
ALLOYS
CESIUM
CHEMICAL REACTIONS
CORROSION
CORROSIVE EFFECTS
CRACKS
ELEMENTS
FLUIDS
GASES
HALOGENS
IODINE
METALS
NONMETALS
RECRYSTALLIZATION
STRESS CORROSION
TEMPERATURE DEPENDENCE
TIN ALLOYS
TUBES
VAPORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS