Published 1978 | Version v1
Journal article

Influence of iodine on the strain and rupture behavior of Zircaloy-4 cladding tubes at high temperatures

Creators

Description

The stress corrosion cracking (SCC) behavior of short tubular Zircaloy-4 specimens by the action of iodine (initial iodine concentration: 0.1 to 10 mg/cm$sup 3$) was investigated out-of-pile between 600 and 1100$degree$C under inert gas conditions. The Zircaloy cladding tube was used as-received and with an inner preliminary oxidation. Moreover, the influence of the uranium oxide (UO$sub 2$) oxygen potential on the SCC behavior was studied. The burst and creep-rupture tests (time-to-rupture $less than equivalent to$15 min) clearly show that the deformation behavior of Zircaloy cladding tubes below 850$degree$C is heavily influenced by the presence of iodine. A failure of Zircaloy tubes takes place that is characterized by little deformation as compared to reference specimens without iodine. With decreasing temperature, the burst strain is greatly reduced. Scanning electron microscope examinations of the rupture surfaces of the cladding tubes show that in the presence of iodine and at burst temperatures below 850$degree$C the cracks in the cladding material are mainly intergranular followed by ductile residual rupture. By contrast, iodine-free specimens are exclusively subject to ductile failure. 48 refs

Additional details

Publishing Information

Journal Title
Am. Soc. Test. Mater., Spec. Tech. Publ.
Journal Issue
no.681
Series
Am. Soc. Test. Mater., Spec. Tech. Publ.
ISSN
0066-0558

Conference

Title
4. symposium on zirconium in the nuclear industry.
Dates
27 - 29 Jun 1978.
Place
Stratford-on-Avon, UK.

Optional Information

Secondary number(s)
CONF-780637--.