Corrosion of Zircaloy-4 tubing in 68OF water (open access)

Corrosion of Zircaloy-4 tubing in 68OF water

Seamless Zircaloy-4 tubing is utilized as fuel rod cladding in light water reactors. Water corrosion tests at 68OF have been performed to determine the corrosion and hydriding characteristics of Zircaloy-4 tubing, fabricated by cold reduction and finished in two metallurgical conditions: a stress-relief anneal (SRA) and a recrystallization anneal (RXA). These corrosion tests revealed differences in the post-transition corrosion product weight gains of the two materials. A computer corrosion model, designated CHORT, was developed from the test data and ascribes the observed difference in material weight gain to an assumed difference in the periodicity of a postulated cyclic buckling of the oxide.
Date: December 1, 1978
Creator: Marino, G. P. & Fischer, R. L.
System: The UNT Digital Library
Susceptibility of unirradiated recrystallized Zircaloy-4 tubing to stress corrosion cracking (open access)

Susceptibility of unirradiated recrystallized Zircaloy-4 tubing to stress corrosion cracking

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.
Date: December 1977
Creator: Polan, N. W. & Tucker, R. P.
System: The UNT Digital Library