Interactions between Stressed Zirconium Alloys and Iodine at 300°C

Zircaloy cladding performance under spent fuel disposal conditions; Progress report, May 1--October 31, 1989

“…The reduction was much more at 427° C, the long-term rupture strength of 15-20% coldworked material dropping from about 150 MPa without iodine to about 50 MPa in the presence of 0.08 mg/cm 2 iodine. [Wood, 1974] addressed several aspects of ISCC of zirconium-based alloys (including Zircaioys 2 and 4). All the tests were performed at 300° C using stressed slotted rings and with iodine concentrations up to 20 mg/cm 2 .…”

Stress-corrosion crack initiation and propagation behavior of Zircaloy-4 cladding under an iodine environment

“…As the fuel burn-up proceeds, the diameter of the cladding is decreased, whereas the outer diameter of the fuel pellet is increased, so that the pellet and the cladding contact each other. Also, the concentration of the iodine inside the fuel rod gradually increases so that the possibility of both mechanical and chemical interaction, which causes SCC, is increased [3][4][5][6][7].…”

Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository

“…Other experiments determined the effect of cadmium, cesium, and iodine vapor at up to 300°C (Hunt et al, 1981;Wood, 1974).…”